ML20059A542
| ML20059A542 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/21/1993 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20059A539 | List: |
| References | |
| NUDOCS 9401030014 | |
| Download: ML20059A542 (4) | |
Text
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i TSCR 93-27 Docket Nos. 50-277 50-278
=l License Nos. DPR-44 DPR-56 1
ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 i
i Docket Nos.
50-277 50-278 l
License Nos. DPR-44 DPR-56 TECHNICAL SPECIFICATION CHANGE REQUEST 93-27
" Main Stack High Range and Reactor Building Roof Vent High Range Radiation Monitors" and i
Deletion of Emergency TSCR 91-10 (Unit 3)
" Temporarily Allow Fuel Loading Without All Control Rods Inserted" (Amendment 168)
List of Attached Pages Unit a Unit 3 77a 77a 225 I
9401030014 931221' PDR ADOCK 05000277 -
P PDfi
Unit 2 TABLE 3.2.F (Cont'd) - SURVEILLANCE INSTRUMENTATION 4
Minimum No.
of Operable Instrument Type Indication Iten Channels Parameter Instrument and Range Action
- 11 2
Suppression Chamber LR-8(9)123A, B Recorder 1-21 ft.
(10)(11)
Water Level (wide range) 12 1
Control Rod Position N/A 28 Volt Indicating )
Lights
)
(1)(2)(3)(4) l l
13 1
Neutron Monitoring N/A SRM, IRM, LPRM
)
}
0-100%
)
14 1
Safety-Relief Valve POAM-2(3)-2-71A-L Acoustic or (5)
Position Indication TE-2(3)-2-113A-L Thermocouple E
15 2
Drywell High RR-8(9)103A, B Recorder l
Range Radiation (7)
Monitors 1-1E(+8) R/hr 16 1
Main Stack High Range RR-0-17-051 Recorder (7)
Radiation Monitor 5
12 10 to 10 CPS (Log Scale) 17 1
Reactor Building Roof RR-2979 (Unit 2)
Recorder Vent High Range Radiation RR-3979 (Unit 3) 10' to 10" CPM (7)
Monitor (Log Scale) 18 2
Drywell Hydrogen 2(3)BS215, 2(3)CS215 Analyzer and Recorder (1)(2)(3)
Concentration Analyzer H2R-4(5)965B, C 0-20% Volume and Monitor
- Notes for Table 3.2.F appear on pages 78 and 78a.
Unit?3-TABLE 3.2.F (Cont'd) - SURVEILLANCE INSTRUMENTATION
-Minitr.um No.
of Operable Type Instrument Indication Item Channels Parameter Instrument and Range Action
- 11 2
Suppression Chamber LR-8(9)123A, B Recorder 1-21 ft.
(10)(11)
Water Level (wide ~ Range) 1 12 1
Control Rod Position N/A 28 Volt Indicating )
Lights
)
(1)(2)(3)(4)
)
13.
1 Neutron Monitoring N/A SRM, IRM, LPRM
)
0-100%
)
14 1
Safety-Relief Valve POAM-2(3)-2-71A-L Acoustic or
'(5)
- Position Indication TE-2(3)-2-113A-L Thermocouple u
5
- t 15 2
Drywell High RR-8(9)103A, B Recorder (7)
Range Radiation 1-1E(+8) R/hr Monitors 16-1 Main Stack High Range RR-0-17-051 Recorder (7)
Radiation Monitor 10 to 10" CPS 5
(Log Scale) 17 1
Reactor Building Roof RR-2979 (Unit 2)
Recorder (7)
Vent.High Range Radiation RR-3979 (Unit 3) 10' to 1033 CPM Monitor (Log Scale) 18 2
Drywell Hydrogen 2(3)BS215, 2(3)CS215 Analyzer and Recorder (1)(2)(3)
Concentration Analyzer H2R-4(5)965B, C 0-20% Volume and Monitor-
- Notes for Table 3.2.F appear on pages 78 and~78a.
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Unit:3 PBAPS j
l
' LIMITING CONDITIONS'FOR OPERATION SURVEILLANCE REOUIREMENTS 3.10 CORE ALTERATIONS 4.10 CORE-ALTERATIONS i
Applicability ADolicability Applies to the fuel handling Applies to the periodic and core reactivity limit-testing ~of those interlocks
- ations, and instrumentation used during refueling and core alterations.
Obiective Obiective i
To ensure-that core reactivity To verify the operability is within the capability of of instrumentation and inter-the' control rods and to pre-locks'used in refueling and vent critically during core alterations.
refueling.
Speci1Jcation Specification A. Refuelina Interlocks A.
Refuelina Interlocks
- l. The reactor mode switch 1.
Prior to any. core altera-shall be locked in the tions within or over the
" Refuel" position during reactor core, the reactor
.i core alterations and the switch " Refuel" position refueling interlocks shall interlocks shall be'func-be operable except as spec-tionally tested.
They shall l
ified in 3.10.A.5 and be tested at weekly intervals 3.10.A.6 below.
thereafter until no longer required.
They shall also be 1
tested following any repair work associated with the interlocks.
2.
Fuel shall not be loaded 2.
Prior to performing control into the reactor core un-rod or control rod drive less all control rods are maintenance on control fully inserted.
cells without removing fuel assemblies, it shall be demonstrated that the core can be made subcritical by a' margin of 0.25 percent Ak at any time during the i
maintenance with the strongest operable control' rod i
I
-225-
.