ML081770201

Tech Spec Pages for Amendment No. 207 Control Room Habitability in Accordance with TSTF-448-A, Rev 3

ML081770201
Person / Time
Site:	Columbia
Issue date:	06/30/2008
From:	NRC/NRR/ADRO/DORL/LPLIV
To:
Lyon, C F, NRR/DLPM, 415-2296
Shared Package
ML081770002	List: ML081770004 ML081770201
References
TAC MD6207
Download: ML081770201 (9)

Text

(3) 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) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, .ource of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

(6) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to store byproduct, source and special nuclear materials not intended for use at Columbia Generating Station. The materials shall be no more than 9 sealed neutron radiation sources designed for insertion into pressurized water reactors and no more than 40 sealed beta radiation sources designed for use in area radiation monitors. The total inventory shall not exceed 24 microcuries of strontium-90, 20 microcuries of uranium-235, 30 curies of plutonium-238, and 3 curies of americium-241.

C. This license shall be deemed to contain -and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3486 megawatts thermal). Items in Attachment 1 shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.207 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

a. For Surveillance Requirements (SRs) not previously performed by existing SRs or other plant tests, the requirement will be considered met on the implementation date and the next required test will be at the interval specified in the Technical Specifications as revised in Amendment No. 149.

Amendment No. 207

- 9a -

(31) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

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

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily-available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders (32) The licensee shall implement and maintain all Actions required by Attachment 2 to NRC Order EA-06-137, issued June 20, 2006, except the last action that requires incorporation of the strategies into the site security plan, contingency plan, emergency plan and/or guard training and qualification plan, as appropriate.

(33) Control Room Envelope Habitability Program (CRE)

Upon implementation of Amendment No.207adopting TSTF-448, Revision 3, the determination of CRE unfiltered air inleakage as required by SR 3.7.3.4, in accordance with TS 5.5.14.c.(i), the assessment of CRE habitability as required by Specification 5.5.14.c.(ii), and the measurement of CRE pressure as required by Specification 5.5.14.d, shall be considered met. Following implementation:

(a) The first performance of SR 3.7.3.4, 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 November 6, 2003, 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.

Amendment No. 207 Revised by letter dated August 9, 2007

- 9b -

(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 November 6, 2003, 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 24 months, plus the 184 days allowed by SR 3.0.2, as measured from March 23, 2006, the date of the most recent successful pressure measurement test, or within 184 days if not performed previously.

Amendment No. 207

CREF System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency F iltra,:ion (CREF) System LCO 3.7.3 Two CREF subsystems shall be OPERABLE.

................- NOTE ------------------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control. I APPLICABILITY: MODES 1, 2, and 3.

During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREF subsystem A.1 Restore CREF 7 days inoperable for reasons subsystem to OPERABLE other than Condition status.

B.

B. One or more CREF B.1 Initiate action to Immediately subsystems inoperable implement mitigating due to inoperable CRE actions.

boundary in MODE 1, 2, or 3. AND.

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

AND (continued)

Columbia Generating Station 3.7.3-I Amendment No; 149.16 .199 o188 207

CREF System 3.7.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Restore CRE boundary 90 days to OPERABLE status, C. Required Action and C.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 Compietion Time of Condition.A or AND B not met in MODE 1.

2, or 3. C.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 /> D. Required Action and D.1 Place OPERABLE CREF Immediately associated Completion subsystem in Time ofCondition A pressurization mode.

not met during OPDRVs. OR D.2 Initiate action to Immediately suspend OPDRVs.

E. Two CREF subsystems E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

(continued)

Columbia Generating Station 3.7.3-2 Amendment No.

14'J,1CO,13o8,o 207

CREF System 3.7.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME.

F. Two CREF subsystems F.1 Initiate action to Immediately inoperable during suspend. OPDRVs.

OPORVs.

OR One or more CREF subsystems inoperable due to inoperable CRE boundary during t)PORVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Operate each CREF subsystem for > 10 31 days continuous hours with the heaters operating.

SR 3.1.3.2 Perform required CREF filter testing in In accordance accordance with the Ventilation Filter, with the VFTP Testing Program (VFTP).

(continued)

Co*],lm!)

i G'-nera Li ng Stat. ion 3.7.3-3 Amendment No.

4* 16,1C 8,1O 99 207

CREF System 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREOUENCY SR 3.1'.3.3 Verify each CREF subsystem actuates on an 24 months actual or simulatec initiation signal.

SR 3.7.3.4 Perform required CRE unfiltered air In accordance inleakage testing in accordance with the with the Control Room Envelope Habitability Program. Control Room Envelope Habitabi lity Program r i Iý) t. on Co I umh i ý) Gt_*npr a tin ,, .) 3. 7.3-4 Amendment No. 149,169,199 207

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Battery Monitoring and Maintenance Program (continued)

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 that 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 the CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Filtration (CREF) System, 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 p-ogram 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) -or the duration of the accident. The program shall include the following elements:

a. The definition of 1he CRE and the CRE boundary.

b. Requirements for maiintaining 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.

(continued)

Columbia Gererjting Station  !.5-13 Amendment No. -4207

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

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 subsystem of the CREF System, operating at the flow rate required by.

the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS. The result:3 shall be trended and used as part of the 24 month assessment of the CRE boundary.

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 for DBA consequences. Unfltered 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 htabitability, determining CRE unfiltered inleakage, and meaEuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

Columbid Generdting Station E.5-14 Amendment No. 207