ML081760118

Technical Specifications, Amendments to Primary Containment Oxygen Concentration and Drywell-to-Suppression Chamber Differential Pressure Limits

ML081760118
Person / Time
Site:	Vermont Yankee
Issue date:	06/23/2008
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
kim J, NRR/ADRO/DORL, 415-4125
References
TAC MD7055
Download: ML081760118 (4)

Text

VYNPS 3.7 LIMITING CONDITIONS FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS (3) The position alarm system will annunciate in the control room if the valve opening exceeds the equivalent of 0.05 inch at all points along the seal surface of the disk.b. Up to two (2) of the ten (10)suppression chamber-drywell vacuum breakers may be determined to be inoperable provided that they are secured, or known to be, in the closed position..c. Reactor operation may continue for fifteen (15) days provided that at least one position alarm circuit for each vacuum breaker is operable and each suppress-ion chamber -drywell vacuum breaker is physically verified to be closed immediately and daily thereafter.

7. Oxygen Concentration

a. The primary containment atmosphere-shall be reduced to less than 4 percent oxygen by volume with nitrogen gas while in the RUN MODE during the time period: i. From 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after thermal power is greater than 15% rated thermal power following startup, to If deficiencies are found such that Specification 3.7.A.6 could not be met, all vacuum breakers shall be inspected and deficiencies corrected.

(3) A drywell to suppression chamber leak rate test shall demonstrate-that with an initial differential pressure of not less than 1.0 psi, the differential pressure decay rate shall not exceed the equivalent of the leakage rate through a 1-inch orifice.7. Oxygen Concentration The primary containment oxygen concentration shall be measured and recorded on a weekly basis.Amendment No. -l-1, 4 232!50 VYNPS 3.7 LIMITING CONDITIONS FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS ii. 24 Hours prior to reducing thermal power to less than 15% rated thermal power prior to the next shutdown.8. If Specification 3.7.A.1 through 3.7.A.6 cannot be met, an orderly shutdown shall be initiated immediately and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.9. If Specification 3.7.A.7 cannot be met, and the primary containment oxygen concentration cannot be restored to less than 4% oxygen by volume within the subsequent 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, reactor thermal power shall be less than 15% rated thermal power within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.10. Drywell/Suppression Chamber d/p a. Differential pressure between the drywell and suppression chamber shall be maintained

>1.7 psid while in the RUN MODE during the time period: i. From 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after thermal power is greater than 15% rated thermal power following startup, to ii. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing thermal power to less than 15% rated thermal power prior to the next shutdown, iii. Except as specified in 3.7.A.10.b.

10. Drywell/Suppression Chamber d/p I a.The differential pressure between the drywell and suppression chamber shall be recorded once per shift.b. The operability of the low differential pressure alarm shall be verified once per week.Amendinent No. -G 232 15!

VYNPS 3,7 LIMITING CONDITIONS FOR OPE.RATION

b. The differential pressure may be reduced to <1.7 psid for a maximum of four hours (period to begin when the AP is reduced to<1.7) during required operabi-lity testing of the HPCI system pump, the RCIC system pump, the drywell-suppression chamber vacuum breakers, and the suppression chamber-reactor building vacuum breakers, and SGTS testing.c. If Specification 3.7.A.10.a cannot be met, and the differential pressure cannot be restored within the subsequent eight hour period, reactor thermal power shall be less than 15%rated thermal power within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.B. Standby Gas Treatment System 4.7 SURVEILLANCE REQUIREMENTS I 1. a. Except as specified in Specification 3.7.B.3.a below, whenever the reactor is in Run Mode or Startup Mode or Hot Shutdown condition, both trains of the Standby Gas Treatment System shall be operable at all times when secondary contain-ment integrity is required.b. Except as specified in Specification 3.7.B.3.b below, whenever the reactor is in Refuel N4ode or Cold Shutdown B. Standby Gas Treatment System 1. At least once per operating cycle, not to.exceed 16 months, the following conditions shall be demonstrated.

a. Pressure drop across the combined HEPA and charcoal filter banks is less than 6 inches of water at 1500 cfm +/-10%.b. Inlet heater input is at least 7.1 kW.Amendment No. 4-I, -44, 9 4-G4, 4-4q, 4-9-, 2-0 232 152 E. Entergy Nuclear Operations, Inc., pursuant to the Act and 10 CFR Parts .30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.3. This 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 below: A. Maximum Power Level Entergy Nuclear Operations, Inc. is authorized to operate the facility at reactor core power levels not to exceed 1912 megawatts thermal in accordance with the Technical Specifications (Appendix A) appended hereto.B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.232 are hereby incorporated in the license. Entergy Nuclear Operations, Inc. snail operate the facility in accordance with the Technical Specifications.

C. Reports Entergy Nuclear Operations, Inc. shall make reports in accordance with the requirements of the Technical Specifications.

D. This paragraph deleted by Amendment No. 226.E. Environmental Conditions Pursuant to the Initial Decision of the presiding Atomic Safety and Licensing Board issued February 27, 1973, the following conditions for the protection of the environment are incorporated herein: Amendment No. 2-96, 208, 2-26, 229 ,-2-,2,4-.232