ML073060406

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Tech Spec Pages for Amendments 252 and 232 Control Room Habitability, Using the Technical Specification Task Force Traveler, TSTF-448, Revision 3
ML073060406
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 10/31/2007
From:
NRC/NRR/ADRO/DORL/LPLII-1
To:
Jervey, Richard 301-415-2728
Shared Package
ML072680874 List:
References
TAC MD5653, TAC MD5654
Download: ML073060406 (21)
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Text

(2) PMrsuant to the Act and I oGFR Part 70, VEPCO to receive, possese, and use at any tire special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation,.as described In the Updated Final Safety Analysis Report; (3) Pursuant to the Act and o"CFR Parts 30, 40, and VEPCO to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor Instrumentation and radiation monitoring equipment calibration, and as fission detectors In amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30,40, and 70, VEPCO 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 calbration or associated with radioactive apparatus or component; and (5) Pursuant to the Act and 10 CFR Parls 30 and 70, VEPCO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

G. This renewed operating license shall be deemed to contain and Is subject to the conditions specified In te following Commission regulations In 10 CFR Chapter 1: Part 20, dctlron 30.64 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Parl 70;, Issubject to all applicable provisions of the Act and to the rules, regulations, and order.of the Commission now or hereafter In effect; and lsubjecl to the additional condtllons specified or Incorporated belovi (1) Maximum Powe Level VEPCO is authodied to operate the Nodh Anna Power Station, Unit No. 1, at reactor core power levels not In excess of 2893 megawatts (thernal).

(2) Technical goeclcllons The Technical Spatllcations contained In Appendix A,as revised through Amendment No.2 5 2 are hereby Incorporated In the renewed license.

The Ucensee shall operate the faciliy Inaccordance with the Technical Speclficatlons..

Renewed License No. NPF-4 Amendment No. 252

For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance subject to the modified acceptance criteria is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.

For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance interval begins upon completion of the last surveillance performed prior to implementation of this amendment.

This license condition is effective as of its date of issuance.

f. Upon implementation of Amendment No. 25Z adopting TSTF-448, Revision 3, the determination of Main Control Room/Emergency Switchgear Room (MCR/ESGR) envelope unfiltered air inleakage as required by TS SR 3.7.10.4 in accordance with TS 5.5.16.c(i), the assessment of MCR/ESGR envelope habitability as required by Specification 5.5.16.c(ii), and the measurement of MCR/ESGR envelope pressure as required by Specification 5.5.16.d, shall be considered met.

Following implementation:

(i) The first performance of SR 3.7.10.4 in accordance with Specification 5.5.16.c(i), shall be within the specified frequency of 6 years plus the 18-month allowance of SR 3.0.2, as measured from September 21, 2003, the date of the most recent successful tracer gas test, as stated in the March 30, 2004 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(ii) The first performance of the periodic assessment of MCRIESGR envelope habitability, Specification 5.5.16.c(ii), shall be within 3 years,

,plus the 9-month allowance of SR 3.0.2, as measured from September 21, 2003, the date of the most recent successful tracer gas test, as stated in the March 31, 2004 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(iii) The first performance of the periodic measurement of MCR/ESGR envelope pressure, Specification 5.5.16.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from February 27, 2007, the date of the most recent successful pressure measurement test, or within 138 days if not performed previously.

NORTH ANNA - UNIT I Renewed License. No. NPF-4 Amendment No. 252

4A)The licensee is authorized to receive from the Surry Power Station, Unit Nos. 1 and 2, possess, and store irradiated Surry Power Station fuel assemblies containing special nuclear material, enriched to not more than 4.1 percent by weight U-235, subject to the following conditions:

a. Surry Power Station fuel assemblies may not be placed in North Anna Power Station, Unit Nos. 1 and 2, reactors.
b. Irradiated fuel shipped to North Anna Power Station shall have been removed from the Surry Power Station reactors no less than 730 days prior to shipment.
c. No more than 500 Surry Power Station irradiated fuel assemblies shall be received for storage at the North Anna Power Station, Unit Nos. 1 and 2, spent fuel pool.

(5) Environmental Protection Plan The Environmental Protection-Plan contained in Appendix B, as revised through Amendment No. 197, is hereby incorporated in the renewed license.

The licensee shall operate the facility in accordance with the Environmental Protection Plan.

D. Fire Protection VEPCO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SER dated February 1979 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

E. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Millstone, North Anna and Surry Power Stations' Security Plan, Training, and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program" with revisions submitted through May 15, 2006.

NORTH ANNA - UNIT Renewed License No. NPF-4 Revised by-letter dated October 20, 2006 Amendment Nn. 299

F. Updated Final Safety Analysis Report (1) The licensee's Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on July 25, October 1, November 4, and December 2, 2002, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than April 1, 2018, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

(2) The Updated Final Safety Analysis Report supplement as revised on July 25, October 1, November 4, and December 2, 2002, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

G. Mitigation Strategy Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(1) Fire fighting response strategy with the following elements:

a. Pre-defined coordinated fire response strategy and guidance
b. Assessment of mutual aid fire fighting assets
c. Designated staging areas for equipment and materials
d. Command and control
e. Training of response personnel (2) Operations to mitigate fuel damage considering the following:
a. Protection and use of personnel assets
b. Communications
c. Minimizing fire spread
d. Procedures for implementing integrated fire response strategy
e. Identification of readily-available pre-staged equipment
f. Training on integrated fire response strategy
g. Spent fuel pool mitigation measures NORTH ANNA - UNIT I Renewed License No. NPF-4 Amendment No. 252

(3) Actions to minimize release to include consideration of:

a. Water spray scrubbing
b. Dose to onsite responders H. This renewed license is effective as of the date of issuance and shall expire at midnight on April 1, 2038.

FOR THE NUCLEAR REGULATORY COMMISSION original signed by:

Samuel J. Collins, Director Office of Nuclear Reactor Regulation Attachments:

1. Appendix A, Technical Specifications
2. Appendix B, Environmental Protection Plan Date of Issuance: March 20, 2003 Amendment Nn-~ ~

NORTH ANNA - U-NiT 1

(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor stortup, sealed sources for reactor Instrumentation and radiation monitoring equipment calibration, and as fission detectors In amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30,40, and 70, VEPCO 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 caliration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30,40. and 70, VEPCO to possess, but not separate, such byproduct and special nudear materials as may be produced by the operation of the facillty.

C. This renewed license shall be deemed to contain and Is subject to the condillons specified In the Commsslon's regulations as set forth In 10 CFR Chapter I and Is subject to all applicable provisions of the Act and to the rules, regulations, and ordeai of the Commfssion now or hereafter In effect; and Is subject to the additional conditions specified or Incorporated below:.

(1) Maximum Power Level VEPCO Is authorized to operate the facility at steady state reactor core power levels not In excess of 2893 megawatts (thermal).

(2) Teihhnical S*ecificatlons The Technical Specifications contained In Appe4dix A, as revised through Amendment No. 2 3 2are hereby Inorporated in the renewed license.

The licensee shai operate the facility In accordance with the Technical Speclflcations.

(3) Aditi0nal Conditions The matters specified In the following conditions shaW be completed to the satisfaction of the Commission within the stated time periods following the Issuance of the conditlon or within the operational restrctions Indicated. The removal of thesd conditions shag be made by an amendment to the renewed license supported by a favorable evaluation by the Commlsslon:

a. If VEPCO plans to remove or to make significant changes In the normal operation of equipment that controls the amount of radioactlvity In effluents from the North Anna Power Station, the 7

Renewed Ucense No NPF-7 Amendment NIo. 232

interval begins upon completion of the last surveillance performed prior to implementation of this amendment.

This license condition is effective as of its date of issuance.

e. VEPCO may operate one lead test assembly containing advanced zirconium-based alloys for one cycle, to a lead rod bumup not exceeding 75,000 MWD/MTU, as described in the licensee's submittal dated February 11, 2002.
f. Upon implementation of Amendment No. 232. adopting TSTF-448, Revision 3, the determination of Main Control Room/Emergency Switchgear Room (MCR/ESGR) envelope unfiltered air inleakage as required by TS SR 3.7.10.4 in accordancewith TS 5.5.16.c(i), the assessment of MCR/ESGR envelope habitability as required by Specification 5.5.16.c(ii), and the measurement of MCR/ESGR envelope pressure as required by Specification 5.5.16.d, shall be considered met.

Following implementation:

(i) The first performance of SR 3.7.10.4 in accordance with Specification 5.5.16.c(i), shall be within the specified frequency of 6 years plus the 18-month allowance of SR 3.0.2, as measured from September 21, 2003, the date of the most recent successful tracer gas test, as stated in the March 30, 2004 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(ii) The first performance of the periodic assessment of MCR/ESGR envelope habitability, Specification 5.5.16.c(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from September 21, 2003, the date of the most recent successful tracer gas test, as stated in the March 31, 2004 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(iii) The first performance of the periodic, measurement of MCR/ESGR envelope pressure, Specification 5.5.16.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from February 27, 2007, the date of the most recent successful pressure measurement test, or within 138 days if not performed previously.

NORTH ANN A UNrT 2 Renewed License No. NPF-7 Amendment No. 232

(4) The licensee is authorized to receive from the Surry Nuclear Power Station, Unit Nos. 1 and 2, possess, and store irradiated Surry Power Station fuel assemblies containing special nuclear material, enriched to not more than 4.1 percent by weight U-235, subject to the following conditions:

a. Surry Power Station fuel assemblies may not be placed in North Anna Power Station, Unit Nos. 1 and 2, reactors.
b. Irradiated fuel shipped to North Anna Power Station shall have been removed from the Surry Power Station reactors no less than 730 days prior to shipment.
c. No more than 500 Surry Power Station irradiated fuel assemblies shall be received for storage at the North Anna Power Station, Unit Nos. 1 and 2, spent fuel pool.

(5) Environmental Protection Plan The Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 178, is hereby incorporated in the renewed license.

The licensee shall operate the facility in accordance with the Environmental Protection Plan.

D. Fire Protection VEPCO shall implement and maintain in effect all provisions of the approved fire protection program as described in the licensee's Updated Final Safety Analysis Report for the-facility and as approved in the SER dated February 1979 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

E. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Millstone, North Anna and Surry Power Stations' Security Plan, Training, and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program" with revisions submitted through May 15, 2006.

N 0RTH INNA - UNIT 2 nRenewed License No. NPF-7 Revised by letter dated October 20, 2006 Amendment No. 232

F. Updated Final Safety Analysis Report (1) The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on July 25, October 1, November 4, and December 2, 2002, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than August 21, 2020, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

(2) The Updated FinalSafety Analysis Report supplement as revised on July 25, October 1, November 4, and December 2, 2002, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by

  • 10 CFR 50.71 (e)(4), following the issuance of this renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteriaset forth in-10 CFR 50.59 and otherwise complies with the requirements in that section.

G. Mitigation Strategy Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(1) Fire fighting response strategy with the following elements:

a. Pre-defined coordinated fire response strategy and guidance
b. Assessment of mutual aid fire fighting assets
c. Designated staging areas for equipment and materials
d. Command and control
e. Training of response personnel (2) Operations to mitigate fuel damage considering the following:
a. Protection and use of personnel assets
b. Communications
c. Minimizing fire spread
d. Procedures for implementing integrated fire response strategy
e. Identification of readily-available pre-staged equipment
f. Training on integrated fire response strategy
g. Spent fuel pool mitigation measures NORTH ANNA - UNIT 2 Renewed License No. NPF-7 Amendment No. 2.32

(3) Actions to minimize release to include consideration of:

a. Water spray scrubbing
b. Dose to onsite responders H-f. This renewed license is effective as of the date of issuance and shall expire at midnight on August 21, 2040.

FOR THE NUCLEAR REGULATORY COMMISSION original signed by:

Samuel J. Collins, Director Office of Nuclear Reactor Regulation Attachments:

1. Appendix A, Technical Specifications
2. Appendix B, Environmental Protection Plan Date of Issuance: March 20, 2003 TTT A T A KIT~Tqm'I Amendment No. 232

MCR/ESGR EVS-MODES 1, 2, 3, and 4 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Main Control Room/Emergency Switchgear Room (MCR/ESGR) Emergency Ventilation System (EVS)-MODES 1, 2, 3, and 4 LCO 3.7.10 Two MCR/ESGR EVS trains shall be OPERABLE.

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

The MCR/ESGR envelope boundary may be opened intermittently under administrative control.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required MCR/ESGR A.1 Restore MCR/ESGR EVS 7 days EVS train inoperable train to OPERABLE for reasons other than status.

Condition B. I B. One or more.required B.1 Initiate action to Immediately MCR/ESGR EVS trains implement mitigating inoperable due to actions.

inoperable MCR/ESGR envelope boundary. AND B.2 Verify mitigating 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> actions ensure MCR/ESGR envelope occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND B.3 Restore MCR/ESGR 90 days envelope boundary to OPERABLE status.

I North An'na Units 1 and 2 3.7.10-1 Amendment Nos. 252, 232

MCR/ESGR EVS-MODES 1, 2, 3, and 4 3.7.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> associated Completion Time of Condition A AND or B not met.

C.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> D. Two required MCR/ESGR D.1 Enter LCO 3.0.3. Immediately EVS trains inoperable for reasons other than Condition B.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each required MCR/ESGR EVS train 31 days for Ž 10 continuous hours with the heaters operating.

SR 3.7.10.2 Perform required MCR/ESGR EVS filter In accordance testing in accordancewith the Ventilation with VFTP Filter Testing Program (VFTP).

SR 3.7.10.3 Not Used SR 3.7.10.4' Perform required.MCR/ESGR Envelope In accordance unfiltered air inleakage testing in with the accordance with the MCR/ESGR Envelope MCR/ESGR Habitability Program. Envelope Habitability Program North Anna Units I and 2 3.7.10-2 Amendment Nos. 252, 232

MCR/ESGR Bottled Air System 3.7.13 3.7 PLANT SYSTEMS 3ý7.13 Main Control Room/Emergency Switchgear Room (MCR/ESGR) Bottled Air System LCO 3.7.13 Three MCR/ESGR bottled air system trains shall be OPERABLE.

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

The MCR/ESGR envelope boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, 3, and 4, During movement of recently irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required MCR/ESGR A.1 Restore MCR/ESGR 7 days bottled air system bottled air system train inoperable for train to OPERABLE reasons other than status.

Condition B.

B. One or more required B.I Initiate action to Immediately MCR/ESGR bottled air implement mitigating system trains actions.

inoperable due to inoperable MCR/ESGR AND envelope boundary in MODE 1, 2, 3, or 4. B.2 Verify mitigating 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> actions ensure MCR/ESGR envelope occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.

AND (continued)

North Anna Units 1 and 2 3.7.13-1 amendment Nos- -252, 2032

MCR/ESGR Bottled Air System 3.7.13 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Restore MCR/ESGR 90 days envelope boundary to OPERABLE status.

C. Two or more required C.1 Initiate action to Immediately MCR/ESGR bottled air implement mitigating system trains actions.

inoperable in MODE 1, 2, 3, or 4 for reasons AND other than Condition B. C.2 Restore at least two 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> MCR/ESGR bottled air system trains to OPERABLE status.

D. Required Action and D.1 Be in'MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> associated Completion Time of Condition A, B AND or C not met in MODE 1, 2, 3, or 4. D.2 Be in MODE 5. 36 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> North Anna Units 1 and 2 3.7.13-2 Amendment Nos. 252, 232

MCR/ESGR Bottled Air System 3.7.13 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Suspend movement of Immediately associated Completion recently irradiated Time of Condition A fuel assemblies.

not met during movement of recently irradiated fuel assemblies.

OR Two or more required MCR/ESGR bottled air system trains inoperable during movement of recently irradiated fuel assemblies.

OR I One or more required bottled air system trains inoperable due to an inoperable MCR/ESGR envelope boundary during movement of recently irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify each required MCR/ESGR bottled air 31 days bank is pressurized to Ž 2300 psig.

SR 3.7.13.2 Verify each required MCR/ESGR bottled air 31 days bank manual valve not locked, sealed, or otherwise secured and required to be open during accident conditions is open.

North Anna Units 1 and 2 3.7.13-3 Amendment Nos. 252, 232

MCR/ESGR Bottled Air System 3.7.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.3 Verify each required MCR/ESGR bottled air 18 months system train actuates on an actual or simulated actuation signal.

SR 3.7.13.4 Verify two required MCR/ESGR bottled air 18 months on a system trains can maintain a positive STAGGERED TEST pressure of Ž_0.05 inches water gauge, BASIS relative to the adjacent areas for, at least 60 minutes.

North Anna Units I and 2 3.7.13-4 AmendmentýNos. 252, 232

MCR/ESGR EVS-During Movement of Recently Irradiated Fuel Assemblies 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Main Control Room/Emergency Switchgear Room (MCR/ESGR) Emergency Ventilation System (EVS)-During Movement of Recently Irradiated Fuel Assemblies LCO 3.7.14 Two MCR/ESGR EVS trains shall be OPERABLE.

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

The MCR/ESGR envelope boundary may be opened intermittently under administrative control.

APPLICABILITY: During movement of recently irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required MCR/ESGR A.1 Restore MCR/ESGR EVS 7 days.

EVS train inoperable train to OPERABLE for reasons other than status.

inoperabl e MCR/ESGR envelope boundary.

B. Required Action and B.1 S.uspend movement of immediately associated Completion recently irradiated Time of Condition A fuel assemblies.

not met.

OR Two required MCR/ESGR EVS trains inoperable.

OR One or more required MCR/ESGR EVS trains inoperable due to inoperable MCR/ESGR envelope boundary.

___________________________________________________________________I North Anna Units I and 2 3.7.14-1 Amendment-Nos. 252, 232

MCR/ESGR EVS-During Movement of Recently Irradiated Fuel Assemblies 3.7.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Operate each required MCR/ESGR EVS train 31 days for - 10 continuous hours with the heaters operating.

SR 3.7.14.2 Perform required MCR/ESGR EVS filter In accordance testing in accordance with the Ventilation *with VFTP Filter Testing Program (VFTP).

SR 3.7.14.3 Perform required MCR/ESGR envelope In accordance unfiltered air inleakage testing in with the accordance with the MCR/ESGR Envelope MCR/ESGR Habitability Program. Envelope Habitability Program North Anna Units 1 and 2 3.7414-2

.Amendment Nos, 2 2

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Containment Leakage Rate Testing Program (continued)

d. Leakage. Rate acceptance criteria are:
1. Prior to entering a MODE where containment OPERABILITY is required, the containment leakage rate acceptance criteria are:

0.60 L for the Type B and Type C tests on a Maximum Path Basis anA ! 0.75 La for Type A tests.

During operation where containment OPERABILITY is required, the containment leakage rate acceptance criteria are:

  • 1.0 La for overall containment leakage rate and
  • 0.60 La for the Type B and Type C tests on a Minimum Path Basis.
2. Overall air lock leakage rate testing acceptance criterion is ! 0.05 La when tested at 2 Pa-
e. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate TesLing Program.
f. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J.

5.5.16 Main Control Room/Emergency Switchgear Room (MCR/ESGR) Envelope Habitability Program A MCR/ESGR Envelope Habitability Program shall be established and implemented to ensure that MCR/ESGR envelope habitability is maintained such that, with an OPERABLE Emergency Habitability System (i.e., MCR/ESGR EVS and MCR/ESGR Bottled Air System), MCR/ESGR envelope occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the MCR/ESGR envelope under design basis accident conditions without (continued)

North Anna Units 1 and 2 5.5-15 Amendment Nos. 252, 232

Programs and Manuals 5.5 5.5 Programs 'and Manuals 5.5.16 Main Control RoomlEmergency Switchgear Room Envelope Habitability program MCR/ESGR) (continued) personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent for the duration of the accident. The program shall include the following elements:

a. The definition of the MCR/ESGR envelope and the MCR/ESGR envelope boundary.
b. Requirements for maintaining the MCR/ESGR envelope boundary in its design condition including configuration control and preventive maintenance.
c. Requirements for (i) determining the unfiltered air inleakage past the MCR/ESGR envelope into the MCR/ESGR envelope in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing MCR/ESGR envelope habitability at the. Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197,. Revision 0.

The following is an exception to Section C.2 of Regulatory Guide 1.197, Revision 0:

Z.C.1 Licensing Bases - Vulnerability assessments for radiological, hazardous chemical and smoke, and emergency ventilation system testing were completed as documented in the UFSAR. The exceptions to the Regulatory Guides (RG) referenced in RG 1.196 (i.e., RG 1.52, RG 1.78, 'and RG 1.183), which were considered in completing the vulnerability assessments, are documented in the UFSAR/current licensing basis. Compliance with these RGs is consistent with the current licensing basis as described in the UFSAR.

d. Measurement, at designated locations, of the MCR/ESGR envelope pressure relative to all external areas adjacent to the MCR/ESGR envelope boundary during the pressurization mode of operation by one train of the MCR/ESGR EVS, operating at the flow rate required by the VFTP, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the MCR/ESGR envelope boundary.

(continued)

North Anna Units 1 and 2 5.5-16 Amendment Nos. 252, 232

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Main Control Room/Emergency Switchgear Room Envelope Habitability Program (MCR/ESGR) (continued)

e. The quantitative limits on unfiltered air inleakage into the MCR/ESGR envelope. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of design basis accident consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of MCR/ESGR envelope occupants to these hazards will be within the assumptions in the licensing basis.
f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing MCR/ESGR envelope habitability, determining MCR/ESGR envelope unfiltered inleakage, and measuring MCR/ESGR envelope pressure and assessing the MCR/ESGR envelope boundary as required by paragraphs c and d, respectively.

North Anna Units I and 2 5.5-17 ciLiLi LkL i4O~ LJL.

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