ML20059A542

Proposed Tech Specs Revising Table 3.2.F, Surveillance Instrumentation, to Accurately Describe Main Stack High Range & Reactor Building Roof Vent Hrrm

ML20059A542
Person / Time
Site:	Peach Bottom
Issue date:	12/21/1993
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20059A539	List: ML20059A536 ML20059A542
References
NUDOCS 9401030014
Download: ML20059A542 (4)

Text

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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 l

" 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 Iten Channels Parameter Indication Instrument and Range Action

• 11 2 Suppression Chamber LR-8(9)123A, B Recorder 1-21 ft.

Water Level (wide range) (10)(11) 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 Position Indication TE-2(3)-2-113A-L (5)

Thermocouple l E 15 2 Drywell High

' RR-8(9)103A, B Range Radiation Recorder (7)

Monitors 1-1E(+8) R/hr 16 1 Main Stack High Range RR-0-17-051 Recorder Radiation Monitor 5 10 to 10 12 CPS (7)

(Log Scale) 17 1 Reactor Building Roof Vent High Range Radiation RR-2979 (Unit 2) Recorder (7)

Monitor RR-3979 (Unit 3) 10' to 10" CPM (Log Scale) 18 2 Drywell Hydrogen 2(3)BS215, 2(3)CS215 Analyzer and Recorder Concentration Analyzer H2R-4(5)965B, C 0-20% Volume (1)(2)(3) 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) u - Position Indication TE-2(3)-2-113A-L Thermocouple 5 Drywell High RR-8(9)103A, B Recorder (7)

-t 15 2 Range Radiation 1-1E(+8) R/hr Monitors 16- 1 Main Stack High Range RR-0-17-051 Recorder (7)

Radiation Monitor 105 to 10" CPS (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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. i 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. .

i Obiective Obiective 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

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