ML20071E917
| ML20071E917 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/11/1983 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20071E866 | List: |
| References | |
| NUDOCS 8303150385 | |
| Download: ML20071E917 (5) | |
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I PBAPS 1.0 DEFINITIONS (cont'd) component, or device to perform its function are also capable of performing their related support function.
Operating - Operating means that a system or component is performing its intended functions in its required manner.
Operating Cycle - Interval between the end of one refueling outage for a particular unit and the end of the next subsequent refueling outage for the same unit.
Primary Containment Integrity - Primary containment integrity means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied:
1.
All primary containment penetrations required to be closed during accident conditions are either:
a)
Capable of being closed by an OPERABLE containment automatic isolation valve system, or b)
Closed by at least one manual valve, blind flange, or deactivated automatic valve secured in its closed position, except as may be provided in Specifications 3.7.D.2 and 4.7.D.2.
Manual valves may be opened to perform necessary operational activities.
2.
At least one door in each airlock is closed and sealed.
3.
All blind flanges and manways are closed.
Protective Action - An action initiated by the protection system when a limit is reached.
A protective action can be at a channel or system level.
Protective Function - A system protective action which results from the protective action of the channels monitoring a particular plant condition.
Rated Power - Rated power refers to operation at a reactor power of 3,293 MWtr this is also termed 100 percent power and is the maximum power level authorized by the operating. license.
Rated steam flow, rated coolant flow, rated neutron flux, and rated nuclear system pressure refer to the values of these parameters when the reactor is at rated power.
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TABLE 3.2.B (COi4TINUED)
INSTRUMENTATION THAT INITIATES OR. CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No.
Of Operable Number of Instru-Instrument Trip Function Trip Level Setting ment Channels Pro Remarks Channels Per vided by Design Trip System (l) 2 Core Spray Pump 6 + 1 sec 4 timers In conjunction with loss Start Timer 10 } 1 sec 4 timers of power initiates 'the
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starting of CSCS pumps.
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LPCI Pump Start Timer 5 + 1 sec 4 timers (Two Pumps) 1 Auto Blowdown Timer 90 $ t i 120 2 timers In conjunction with Low Reactor Water Level, i
i High Drywell Pressure C
and LPCI or Core Spray I
Pump running interlock, initiates Auto Blowdown.
2 RHR (LPCI) Pump 50 + 10 psig l
Discharge Pressure 4 channels Defers ADS actuation pending confirmation of Interlock Low Pressure Core Cooling system operation (LPCI Pump running interlock.)
2 Core Spray Pump 185 + 10 psig 4 channels Defers ADS actuation
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Discharge Pressure pending confirmation of Interlock Low Pressure Core cooling,
system operation (Core Spray Pump running interlock.)
TABLE 3.14.C.1 l
l FIRE DETECTORS Detector Type /
Minimum Detectors Location Designation (l)
Operable UNIT 2 Primary Containment (2) (3)
S1, S2, S8 3
CRD Area (135') Rms. 208, 209, S7A, S8A, S9A,S10A 13 212 SilA,S12A,S13A,S14A S15A,S16A,S17A,S18A S19A,S20A I
Isol. Valve Compt.(135')Rm.204 S21A 1
Opsrating Area (165')Rm.402,403 S31A,S32A,S33A,S34A 12 S35A,S36A,S37A,S38A S39A,S40A,S41A,S42A S43A Leydown Area (195')Rm.501,502 S45A,S46A,S47A,S48A 7
508 S49A,S50A,S51A,S52A Vent. Equip. Area (195')Rm.506 S53A, S54A 2
Vant Stack Rad. Mon.-Refuel S58A, S59A 2
floor (234')
HPCI Room S78 1
H5, H6, H7 (See 3.14.B.l.c)
RCIC Room S45, S46 2
Reactor Bldg. Sump Area S79 1
Core Spray Pump Rooms S41, S42, S43, S44 4
Vac. Breaker Area-Rm, 107,108 S91, S92, S93 3
RHR Rooms Room 101 S30, S31, 832 3
Room 102 S33, S34, S35 3
Room 103 S36, S37, S38 3
Room 104 S39, S40 2
Torus Area S83,S84,S85,S86 7
S87,S88,S89,S90 M-G Set Lube Oil Rm (Rm 105)
S94,S95,S96,S97,S98 4
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TABLR 3.14.r.1 FIRE DETECTORS Detector Type /
Minimum Detectors T,oca ti on Designation (1)
Onorable Recire. Pump MC Set Room S15, S16, S17 5
SIR, S19, S20
'Emerg. Switchgear Rooms S11, S12, S13, S14 4
. Battery Roomo Room 21n S70, S71 2
Room'225 S68,.S69 2
13KV Switchgoar Area (116')
S72, S73, S74 3
.IIPSW~ Pump Room S390 1
Il>TT P 3 Primary Containment (2)(3)
S103, S104, S106 3
CRD Area (135') Rms. 250 S166,S167,SIG8,S169 13 259, ?57 S170,S171,S172,S173 S174,S175,S176,S177 S178,S179 Tsol. Valve compt.
S181 1
.(135') Rm 249 Operating Area (165')
S182, SIR 3,S184,S195 12 Rm. 443, 444 S186,9187,S189,S189 S190,S191,S192,S193 S194 Laydown Area (195')
S196,S197,S198,S199 7
Rm. 517, 518, 523 S103A,S104A,S105A,S106A
.Vont. Equip Area (195')
S107A, S10RA 2
Rm. 520 Vant' Stack Rad. Mon.-Refuel S109A, S110A 2
floor (234')
TIPCT Room S14R 1
!!115, IT116, 11117 (See 3.14.n.1.c)
PCTC Room S131, S132 2
Reactor Ridg. Sump Area S149 1
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PBAPS 6.13,,, High Radiation Area 6.13.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CFR 20:
a.
Each High Radiation Area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Work Permit.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
1.
A radiation monitoring device which c'ontinuously indicates the radiation dose rate in the area.
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2.
A radiation monitoring device which continuously intergrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate levels in the area have l
been established and personnel have been made knowledgeable of them.
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3.
An individual qualified in radiation j
protection procedures who is equipped with a fadiation dose rate monitoring device.
This i
I individual shall be responsible for providing
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positive control over activities within the j
area and shall perform periodic radiation Q
surveillance at the frequency specified by the plant Health Physicist or his designee on the
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Radiation Work Permit.
f b.
Each High Radiation Area in which the intensity of radiation is greater than 1000 mrem /hr shall be subject to the provisions of 6.13.1 (a) above.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Superintendent, the Shift i
Supervisor or the Senior Health Physicist.
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