ML20154H424
| ML20154H424 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/09/1988 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20154H387 | List: |
| References | |
| NUDOCS 8809220001 | |
| Download: ML20154H424 (5) | |
Text
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7.
The Containment Purge and Vent System shall be operable.
The Contair. ment Purge and Vent System shall be demonstrated operable within 4 days prior to the start of and at least once per 7 days during refueling operations by verifying that Containment Purge and Vent isolation occurs on manual initiation and on high radiation test signal.
8.
With the Containment Purge and Vent System inoperable, close the Purge and Vent containment penetrations.
9.
If any of the specified limiting conditions in sections 1, 2, 3, 4, 5, and 6 are not met, refueling of the reactor shall cease. Work shall be initiated to correct the violated conditions so that the specified limits are met, and no operations which may increase the reactivity of the core shall be made.
Basis The equipment and general procedures to be utilized during refueling are discussed in the Final Safety Analysis Report.
Detailed instructions, the above specified precautions, and the design of the fuel handling equipment incorporating built-in interlocks and safety fe: cures, provide assurance that no incident could occur during the refueling operations that would result in a hazard to public health and safety.(1)
Whenever changes are not being made in core geometry, one flux monitor is sufficient.
This permits maintenance of the instrumentation.
Continuous monitoring of radiation levels (2. above) and neutron flux provides immediate indication of an unsafe condition.
The residual heat pump is used to maintain a uniform boron concentration.
The shutdown margin indicated in Part 5 will keep the core suberitical, even if all control rods were withdrawn from the core.
During refueling, the reactor refueling cavity is filled with approximately 275,000 gallons of borated water.
The boron concentration of this water is sufficient to maintain the reactor subcritical approximately by 5% ok/k in the cold condition with all rods 8809220001 000909
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PDR ADOCK 05000266 P
PNU Unit 1 - Amendment No.
15.3.8-2 Unit 2 - Amendment No.
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inserted.(2) Periodic checks of refueling water boron concentration insure that proper shutdown margin is maintained.
Part 6 allows the control room operator to inform the manipulator operator of any impending unsafe condition detected from the main contrc,1 board indicators during fuel movement.
During the refueling operation a substantial number of station personnel and perhaps some regulatory people will be in the containment.
The requirements are to prevent an unsafe amount of radioactivity from escaping to the environment in the case of a refueling accident, and also to allow safe avenues of escape for the personnel inside the containment as required by the Wisconsin Department of Industry, Labor and Human Relations.
To provide for these requirements, the personnel locks (both doors) are open for the normal refueling operations with a third temporary door which opens outward installed across the outside end of the personnel lock.
This hollow metal third door is equipped with weather stripping and an automatic door closer to minimize the exchange of inside air with the outside atmosphere under the very small differential pressures expected while in the refueling condition.
Upon sounding of the containment evacuation alarm, all personnel will exit through the temporary door (s) and then all personnel lock doors shall be closed.
As soon as possible, the fuel transfer gate valve shall be closed to back up the 30 foot water seal to prevent escape of fission products.
The spent fuel storage pool at the Point Beach Nuclear Plant consists of a single pool with a four foot thick reinforced concrete divider wall which separates the pool into a north half and south half.
The divider wall is notched to a point sixteen feet above the pool floor to allow transfer of assemblies from one half of the pool to the other.
Previous Technical Specifications in this section had addressed maximum load limits and limitations on load movements by the auxiliary building crane over a spent fuel pool.
These specifications were deleted upon modification of the crane to meet the single-failure proof criteria outiined in NUREG-0612.
References (1) FSAR - Section 9.5.2 (2) FSAR - Table 3.2.1-1 l
r Unit 1 Amendment No.
15.3.8-3 Unit 2 Amendment No.
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TABLE 15.7.3-2 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION Minimum' Channels Instrument-Operable Action 1.
Gas D'ecay Tank System a.
RE-214, Noble Gas (Auxiliary 1
Note 1 Building Vent Stack), or RE-315 Noble Gas (Auxiliary Building Vent SPING) b.
Gas Decay Tank Flow 1
Note 4 Measuring Meter 2.
Auxiliary Building Ventilation Systet s
a.
RE-214, Noble Gas (Auxiliary 1
Note 6 Building Vent Stcck) or Re-315, j
Noble Gas (Auxiliary Building Vent SPING) b.
Isokinetic Iodine and Particulate -
1 Note 5 Continuous Air Sampling System 3.
Condenser Air Ejector System i
a.
RE-225, Noble t.2< (Combined Air 1
Note 6 Ejector Discharge Monitor); or RE-215, Noble gas (Air Ejector Monitors - 1 per unit); or RE-214, Noble Gas (Auxiliary Building Vent Stack); or RE-315,' Noble Gas (Auxiliary Building Vent SPING) b.
Flow Rate Monitor - Air Ejectors 1
Note 9 I
4.
Containment Purge and Vent System l
l l
a.
RE-212, Noble Gas Monitors 1
Note 6 (1 per unit); or RE-305, Noble Gas (Purge Exhaust SPING - 1 per unit) b.
30 cfm Forced Vent Path Flow Indicators 1
Note 9 i
Unit 1 Amendment 15.7.3-4 Unit 2 Amendment 1
4 TABLE 15.7.4-2 RADI0 ACTIVE GASE0US EFFLUENT MONIl0 RING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Functional Source Channel Description Check Calibrate Test Check 1.
Gas Decay Tank System
- a. RE-214, Noble Gas (Auxiliary Building Vent Stack)
D R
Q M
- b. Gas Decay Tank Flow Measuring Device P
R NA NA 2.
Auxiliary Building Ventilation System
- a. RE-214, Noble Gas (Auxiliary Building Vent Stack)
D R
Q M
- b. RE-315, Noble Gas (Auxiliary Building SPING)
D R
Q M
- c. Isokinetic Iodine and Particulate Continuous Air Sampling System W
R NA NA 3.
Condenser Air Ejector System
- a. RE-225, Noble Gas (Combined Air Ejector Discharge)
D R
Q M
- b. RE-215, Noble Gas (Air Ejectors - 1 per unit)
D R
Q M
- c. Flow Rate Monitor - Air Ejectors (1 per unit)
D R
NA NA 4.
Containment Purge and Vent System l
- a. RE-212, Noble Gas (1 per unit)
D R
Q M*
- b. 30 cfm Vent Path Flow Indicator P/D R
NA NA Unit 1 Amendment Unit 2 Amendment
O.
E
'.6-2 RADI0 ACTIVE GASEOUS WW
_fiFLING AND ANALYSIS PROGRAM Lower Level Sampling Minimum Type of of Detectioni Gaseous Release Type Frequency Analysis Frequency Activity Analysis (pCi/cc)
-4
- 1. Gas Decay Tank Prior to Prior to Release Gamma Emitters 1 x 10 Release 1x10[f
- 2. Containment Purge or Prior to Purge Prior to Purge Gamma Emitters Continuous Vent or Vent or Vent Tritium 1 x 10 Weekly Analysis Gamma Emitters 1x10[
- 3. Continuous Releases:
Continuous 3 of Charcoal and I-131 1 x 10
- a. Unit 1 Containment Purge and Vent Particulate Samples
- b. Unit 2 Containment Purge and Vent
_yy
- c. Drumming Area Vent Monthly Composite Gross Alpha 1 x 10
- d. Gas ftripper Building Vent of Particulate Sample
- e. Auxiliary Building Vent
_yy of Particulate Sample
-6 Noble Gas Monitor Noble gases 1 x 10 Gross Beta or gamma 4
-4 Monthly Monthly Gamma Emitters 1 x 10 (Grab)
-6 Monthly Tritium 1 x 10 Unit 1 Amendment Unit 2 Amendment l
l t
_