ML071720254

H. B. Robinson Steam Electric Plant, Unit 2 - Technical Specifications Changes Related to Containment Peak Pressure (TAC No. MD2682)

ML071720254
Person / Time
Site:	Robinson
Issue date:	06/15/2007
From:	NRC/NRR/ADRO/DORL/LPLII-2
To:
References
TAC MD2682
Download: ML071720254 (4)

Text

-3-neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;D. 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 and equipment calibration or associated with radioactive apparatus or components; E. 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 operation of the facility.3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations:

10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR 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: A. Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215 are hereby incorporated in the license.The licensee shall operate the facility-in accordance with the Technical Specifications.

(1) For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.Renewed Facility Operating License No. DPR-23 Amendment No.21 5 Isolation Valve Seal Water System 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Isolation Valve Seal Water (IVSW) System LCO 3.6.8 APPLICABILITY:

The IVSW System shall be OPERABLE.MODES 1. 2, 3, and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. IVSW system A.1 Restore IVSW system 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable, to OPERABLE status.B. Required Action B.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 /> and associated Completion Time AND not met.B.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 /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Verify IVSW tank pressure is > 46.2 psig. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.6.8.2 Verify the IVSW tank volume is 31 days 85 gallons.(continued)

I HBRSEP Unit No. 2 3.6-20 Amendment No. 215 Isolation Valve Seal Water System 3.6.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.8.3 Verify the opening time of each air In accordance operated header injection valve is within with the limits. Inservice Testing Program SR 3.6.8.4 Verify each automatic valve in the IVSW 18 months System actuates to the correct position on an actual or simulated actuation signal.SR 3.6.8.5 Verify the IVSW dedicated nitrogen 18 months bottles will pressurize the IVSW tank to k 46.2 psig.SR 3.6.8.6 Verify IVSW seal header flow rate is: 18 months a. 5 52.00 cc/minute for Header A, b. 5 16.50 cc/minute for Header B, c. 32.50 cc/minute for Header C, and d. 23.00 cc/minute for Header D.I HBRSEP Unit No. 2 3.6-21 Amendment No. 215 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakage Rate Testing Program This program provides controls for implementation of the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions for Type A testing. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception:

a. NEI 94-01 -1995, Section 9.2.3: The first Type A test performed after the April 9, 1992, Type A test shall be performed no later than April 9, 2007.Type B and C testing shall be implemented in the program in accordance with the requirements of 10 CFR 50, Appendix J, Option A.The peak containment pressure, Pa, is specified as the containment design pressure of 42 psig, which exceeds the peak calculated containment internal pressure for the design basis loss of coolant accident.The maximum allowable containment leakage rate. La, at Pa, shall be 0.1% of the containment air weight per day.Leakage rate acceptance criteria are: a. Containment leakage rate acceptance criteria is _ 1.0 La.During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are _ 0.60 La for the Type B and Type C tests, and s 0.75 La for Type A tests.The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.HBRSEP Unit No. 2 5.0-24 Amendment No.215 HBRSEP Unit No. 2 5.0-24 Amendment No.215