ML080510374

Tech Spec Pages for Amendments 281 and 163 Control Room Envelope Habitibility in Accordance with Technical Specification Task Force Traveler 448

ML080510374
Person / Time
Site:	Beaver Valley
Issue date:	02/15/2008
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
Morgan N, NRR/DORL, 415-3650
References
TAC MD6628, TAC MD6629
Download: ML080510374 (9)

Text

(3) FENOC, 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; (4) FENOC, 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; (5) FENOC, pursuant to the Act and 10 CFR Parts 30, 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 amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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 FENOC is authorized to operate the facility at a steady state reactor core power level of 2900 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 281, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Auxiliary River Water System (Deleted by Amendment No. 8)

Amendment No. 281

CREVS 3.7.10 3.7 PLANT SYSTEMS 3.7.10 Control Room Emergency Ventilation System (CREVS)

LCO 3.7.10 Two CREVS trains shall be OPERABLE.

- NOTE -

The control room envelope (CRE) boundary may be opened I.

intermittently under administrative control.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required CREVS train A.1 Restore required CREVS' 7 days inoperable for reasons train to OPERABLE status.

other than Condition B.

B. One or more required B.1 Initiate action to implement Immediately CREVS trains inoperable mitigating actions.

due to inoperable CRE boundary in MODE 1, 2, 3, AND or4.

B.2 Verify mitigating actions 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ensure CRE occupant radiological exposures will not exceed liniits and CRE occupants are protected from chemical and smoke hazards.

AND B.3 Restore CRE boundary to 90 days OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Beaver Valley Units 1 and 2 3.7.10- 1 Amendments 281 / 163

CREVS 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Place OPERABLE CREVS Immediately associated Completion train in emergency Time of Condition A not- pressurization mode of met during movement of operation.

recently irradiated fuel assemblies or during OR movement of fuel assemblies over recently D.2 Suspend movement of Immediately irradiated fuel assemblies, recently irradiated fuel assemblies and movement of fuel assemblies over recently irradiated fuel assemblies.

E. Two required CREVS E.1 Suspend movement of Immediately trains inoperable during recently irradiated fuel movement of recently assemblies and movement irradiated fuel assemblies of fuel assemblies over or during movement of fuel recently irradiated fuel assemblies over recently assemblies.

irradiated fuel assemblies.

OR One or more required CREVS trains inoperable due to an inoperable CRE boundary during movement of recently irradiated fuel assemblies or during movement of fuel assemblies over recently irradiated fuel assemblies.

F. Two required CREVS F.1 Enter LCO 3.0.3. Immediately trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

Beaver Valley Units 1 and 2 3.7.10-2 Amendments 281 / 163

CREVS 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CREVS train for >_15 minutes with 31 days heaters operating.

SR 3.7.10.2 Perform required CREVS filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.7.10.3 Verify each CREVS train actuates on an actual or 18 months simulated actuation signal.

SR 3.7.10.4 Perform required CRE, unfiltered air inleakage testing in In accordance accordance with the Control Room Envelope with the Control' Habitability Program. Room Envelope Habitability Program Beaver Valley Units 1 and 2 3.7.10 -3 Amendments 281 / 163 I

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Battery Monitoring and Maintenance Program This Program provides for-battery restoration and maintenance, which includes the following:

a. Actions to restore battery cells with float voltage < 2.13 V,

b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates, and

c. Actions to verify the remaining cells are _ 2.07 V when a cell or cells have been found to be < 2.13 V.

5.5.14 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS), CRE 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 CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE 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 CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREVS, 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 periodic assessment of the CRE boundary.

Beaver Valley Units 1 and 2 5.5 -20 Amendments 281 / 163

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Control Room Envelope Habitability Program (continued)

e. The quantitative limits on unfiltered air inleakage into the CRE. 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 DBA consequences.

Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE 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 CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

Beaver Valley Units 1 and 2 5.5 -21 Amendments 281 /163 I

APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-66 FirstEnergy Nuclear Operating Company and FirstEnergy Nuclear Generation Corp. shall comply with the following conditions on the schedules noted below:

Amendment Additional Condition Implementation Number Date Thniary 15,2008 281 Initial Performance of New Surveillance and Assessment Requirements Upon implementation of Amendment No. 281 adopting TSTF-448, The Revision 3, the determination of control room envelope (CRE) amendment unfiltered air inleakage as required by Surveillance Requirement shall be (SR) 3.7.10.4, in accordance with Specification 5.5.14.c(i), the implemented assessment of CRE habitability as required by Specification within '120 days 5.5.14.c(ii), and the measurement of CRE pressure as required by from date of Specification 5.5.14.d, shall be considered met. Following issuance implementation:

(a) The first performance of SR 3.7.10.4, in accordance with Specification 5.5.14.c(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of

-, SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.14.c(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.14.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test.

5 Amendment No. 281

- 3a -

transactions shall have no effect on the license for the BVPS Unit 2 facility throughout the term of the license.

(b) Further, the licensees are also required to notify the NRC in writing prior to any change in: (i) the term or conditions of any. lease agreements executed as part of these transactions; (ii) the BVPS Operating Agreement, (iii) the existing property insurance coverage for BVPS Unit 2, and (iv) any action by a lessor or others that may have adverse effect on the safe operation of the facility.

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations set forth in 10 CFR Chapter 1 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 FENOC is authorized to operate the facility at a steady state reactor core power level of 2900megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 163, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. FENOC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 163

APPENDIX D ADDITIONAL CONDITIONS OPERATING LICENSE NO. NPF-73 FirstEnergy Nuclear Operating Company, FirstEnergy Nuclear Generation Corp., Ohio Edison Company, and The Toledo Edison Company shall comply with the following conditions on the schedules noted below:

Amendment Additional Condition Implementation Number Date Initial Performance of New Surveillance and Assessment F*brwry 15, 2MM8 163 Requirements Upon implementation of Amendment No. 163 adopting TSTF-448, The Revision 3, the determination of control room envelope ,(CRE) amendment unfiltered air inleakage as required by Surveillance Requirement shall be (SR) 3.7.10.4, in accordance with Specification 5.5.14.c(i), the implemented assessment of CRE habitability as required by Specification within 120 days 5.5.14.c(ii), and the measurement of CRE pressure as required by from date of

'Specification 5.5.14.d, shall be considered met. Following issuance implementation:

(a) The first performance of SR 3.7.10.4, in accordance with Specification 5.5.14.c(i), shall be within the specified Frequency of 6 years, plus the 18-month allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is'greater than 6 years.

(b) The first performance of the periodic assessment of CRE habitability, Specification 5.5.14.c(ii), shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from the date of the most recent successful tracer gas test, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.14.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test.

5 Amendment NO. 163