ML19322B607
| ML19322B607 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 02/05/1976 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19322B605 | List: |
| References | |
| NUDOCS 7912040634 | |
| Download: ML19322B607 (3) | |
Text
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O 3.6 REACTOR BUILDING Applicability Applies to the containment when the reactor is in conditions other than refueling shutdown.
Objective To assure containment integrity during shutdown (other than refueling shutdown), startup and operation.
Specification 3.6.1 Containment integrity shall be maintained whenever all three (3) of the following conditions exist:
Reactorcoolantpressureis300psfgorgreater a.
b.
Reactor coolant temperature is 200 F or greater c.
Nuclear fuel is in the core 3.6.2 Containment integrity shall be maintained whenever the reactor is suberitical by less than 1% Ak/k or whenever positive reactivity insertions are being made which would result in the reactor being suberitical by less than 1% Ak/k.
3.6.3 Exceptions to 3.6.1 and 3.6.2 shall be as follows:
If either the personnel or emergency hatches become inoperable, a.
except as a result of an inoperable door gasket, the hatch shall be restored to an operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
If a hat.ch is inoperable due to an inoperable door gasket:
1 1.
The remaining door of the affected hatch shall be closed and sealed.
If the inner door gasket is inoperable, momentary passage (not to exceed 10 minutes for each opening) is permitted through the outer door for repair or test of the inner door, provided that the outer door gasket is leak tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after opening of the outer door.
2.
The hatch shall be restored to operable status within seven days or the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
b.
A containment isolation valve may be inoperable provided either:
1.
The inoperable valve is restored to operable status within four hours.
2.
The affected penetration is isolated within tour hours by the use of a deactivated automatic valve secured and Idhked in the isolated position.
3.6-1 191s040 k
f
\\
3.3.6 Except tons to 3.3.5 shall be as follows:
(a)
Bath core flooding tanks shall be operation labove 800 psig.
a (b)
Bo~th motor-operated valves associated with th tamks shall be fully open above 800 psi e core flooding g.
(c)
One pressure instrument channel and one I channel per core flood tank shall be operablcvel instrument e above 800 psig.
(d) One shall be permitt'ed to be out of service for sevreac ng unit both reactor building spray pumps and associat d en days provided headers are in service at e
the same time.
spray nozzle Basen be made critical, adequate engineered safetThe require before the reactor can at, high pressure injection pumps and two low presy features are operable.
specified.
- However, Two to the reactor in the event of a loss ofonly one of each is nece coolant core flooding tanks are required as a single c rgency
-coolant accident.
Both insufficient inventory to reflood the core ore flood tank has (1)
The borated water storage tanks are used fo r two purposes:
(a)
As a supply of borated water for accident c onditions.
(b) during refueling operation.As a supply of borated water for floodin (2) e fuel transfer canal Three-hundred fifty thousand (350,000) gall 46 feet in the BWST) are required to supplyons of borated water (a level of reactor building spray in the event of a loss-ofemergency core cooling and This amount water storage tank capacity offulfills requirements for emergency core c-cor ooling.
The borated 388,000 gallon requirements.
Heaters maintain the borated water supply ats is based on refuelin to prevent freezing.
The boron concentration is set at a temperature required to maintain the core control rods in the core.
1 percent suberitical at the amount of boron minimum value specified in the tanks isThis concentration is 1,338 ppm boron wh 1,800 ppm boron.
e the When the reactor is critical, maintenance i and 3.3.6.
surveillance testing as required by Technical fOperability of the s assured by periodic maintenance period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is accept pecification 4.5.
The of failure of redundant equipment during that abic, based on a low likelihood period.
Ithasgeenshownfortheworstdesignbasisl 14.1 ft hot Icg break) that oss-of-coolant accident (a maintenance period of seven days is acceptablbe exce not erable.
Therefore, a cooling fan and its associated cooling unit e for one reactor building
. (3) 3.3-3 l
In the event that the need for emergency core cooling should occur, functioning of one train (one high pressure injection pump, one low pressure injection pump, and both core flooding tanks) will protect the core and in the event of a main coolant loop severence, limit the peak clad temperature to less than 2,300"F and the metal-water reaction to that representing less than 1 percent of the clad.
Three low pressure service water pumps serve Oconee Units 1 and 2 and two low pressure service water pumps serve Oconee Unit 3.
There is a manual cross-connection on the supply headers for Units 1, 2, and 3.
One low pressure service water pump per unit is required for normal operation.
The normal operating requirements are greater than the emergency requirements following a loss-of-coolant accident.
A single train of reactor building penetration room ventilation equipment retains full capacity to control and minimize the release of radioactive materials from the reactor building to the environment in post-accident conditions.
REFERENCES (1)
FSAR, Section 14.2.2.3 (2)
FSAR, Section 9.5.2 (3)
FSAR, Supplement 13 (4)
FSAR, Section 6.4 l
l V
3.3-4