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 OPERATION CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS (3) The position If alarm system deficiencies will are found annunciate in such that the control Specification room if the 3.7.A.6 could valve opening not be met, exceeds the all vacuum equivalent of breakers 0.05 inch at shall be all points inspected and along the deficiencies seal surface corrected.

of the disk.

(3) A drywell to

b. Up to two (2) of suppression the ten (10) chamber leak suppression chamber rate test

- drywell vacuum shall breakers may be demonstrate-determined to be that with an inoperable provided initial that they are differential secured, or known pressure of to be, in the not less than closed position. 1.0 psi, the differential

.c. Reactor operation pressure may continue for decay rate fifteen (15) days shall not provided that at exceed the least one position equivalent of alarm circuit for the leakage each vacuum breaker rate through is operable and a 1-inch each suppress-ion orifice.

chamber - drywell vacuum breaker is physically verified to be closed immediately and daily thereafter.

7. Oxygen Concentration 7. Oxygen Concentration

a. The primary The primary containment containment oxygen concentration atmosphere-shall be shall be measured and reduced to less recorded on a weekly than 4 percent basis.

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 Amendment No. -l-1, 4 232 !50

VYNPS 3.7 LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS OPERATION 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 10. Drywell/Suppression Chamber d/p I

a. Differential pressure between a. The differential the drywell and pressure between suppression chamber the drywell and shall be maintained suppression chamber

>1.7 psid while in shall be recorded the RUN MODE during once per shift.

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 b. The operability of than 15% rated the low thermal power differential following pressure alarm startup, to shall be verified once per week.

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.

Amendinent No. -G 232 15!

VYNPS 3,7 LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS 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 I 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 B. Standby Gas Treatment System

1. a. Except as specified 1. At least once per in Specification operating cycle, not to.

3.7.B.3.a below, exceed 16 months, the whenever the reactor following conditions is in Run Mode or shall be demonstrated.

Startup Mode or Hot Shutdown condition, a. Pressure drop across both trains of the the combined HEPA Standby Gas and charcoal filter Treatment System banks is less than shall be operable at 6 inches of water at all times when 1500 cfm +/-10%.

secondary contain-ment integrity is b. Inlet heater input required. is at least 7.1 kW.

b. Except as specified in Specification 3.7.B.3.b below, whenever the reactor is in Refuel N4ode or Cold Shutdown 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