ML18139B670
| ML18139B670 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1981 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139B669 | List: |
| References | |
| NUDOCS 8201070116 | |
| Download: ML18139B670 (2) | |
Text
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TS 3.8-1 3.8 CONTAINMENT Applicability Applies to the integrity and operating pressure of the reactor containment.
Objective To define the limiting operating status of the reactor containment for unit operation.
Specification A.
Containment Integrity and Operating Pressure
- 1.
The containment integrity, as defined in TS Section 1.0, shall not be violated, except as specified in Specification 3.8.A.2, below, unless the reactor is in the cold shutdown condition.
- 2.
The reactor contain~ent shall not be purged while _the. reactor, is operating, except as stated in Specification 3.8.A.3.
- 3.
During the plant startup, the remote manual valve on the steam jet air ejector suction line may be open, if under administrative control, while containment vacuum is bein~ established~
The Reactor Coolant System temperature and pressure must not exceed 350°F and 450 psig, respectively, until the air partial pressure in the containment has been reduced to a value equal to, or below, that specified in TS Fig. 3.8-1.
The containment purge valves shall not be open above 200°F.*
- 4.
The containment integrity shall not be violated when the reactor vessel head is unbolted unless a shutdown margin greater than 10 percent A k/k is maintained.
This is only an interim change and will be removed after the qualification of the valves.
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TABLE 4.l.2A (CONTINUED)
DESCRIPTION
- 16.
Reactor Vessel Overpressure Mitigating System (except
- backup air supply)
- 17.
Reactor Vessel Overpressure Mitigating System Backup Air Supply
- 18.
Primary Coolant System Pressur~ Isolation Valves TEST Functional and Setpoint Setpoint Functional
- 19.
Containment Purge MOV Leakage Functional Test FREQUENCY Prior to decreasing RCS temperature below 350°F and monthly while the RCS is(350°F and the Reactor Vessel Heat is bolted.
Refueling
- 1.
Periodic leakage (a) on each valve listed in Specification 3.1.C. 7a shall be
_accomplished prior to entering power operation condition after every time the plant is placed in the cold shutdown condition for refueling, after each time the plant is placed in cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been.accomp-lished in the preceeding 9 months, and prior to returnlng the valve to service after maintenance, repair or replacement
.work is performed.
Semi-Annual (Unit at power or shutdown) if purge valves are operated during interval (c) l (a)
To satisfy ALARA requirements, lea~age may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance. with the leakage criteria.
(b)
Minimum differential test pressure shall not be below 150 psid.
(c) Refer to Section 4.4 for acceptance criteria.
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