ML20058B371

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Proposed Tech Specs Re RETS
ML20058B371
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 10/19/1990
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20058B369 List:
References
NUDOCS 9010300154
Download: ML20058B371 (14)
v • d • e


Text

{{#Wiki_filter:* INDEX l DESIGN FEATURES-SECTION PAGE 5.1 SITE 5 Exclusion Area.................................................. 5-1 Figure 5.1.1-1 Exclusion Area........................ 5-2 low Population Zone............................................. 5-1 Figure 5.1.2-1 Low Population Zone................... 5-3 f Meps Defining UNRESTRICTED AREAS and SITE BOUNDARY for Radioactive Gaseous and Liquid Effluents................... 5-1 ~ figure 5.1.3-la Map Defining UNRESTRICTED AREAS for Radioactive Gaseous and Liquid Effluents.............. 5-4 figure 5.1.3-lb Map Defining UNRESTRICTED AREAS for i Radioactive Gaseous and Liquid Effluents.............. 5-5 (0eleted)....................................................... 5-1 The figure on page 5-6 has been intentionally omitted.- Refer to note on page 5-6................... 5-6 5.2 CONTAINMENT. Configuration................................................... 5-1 ,5 De sign Temperature and Pres sure................................. 5-1 s-.-..,_.. --.. S e co nd a ry C o n t a i nme n t.. r........'.......... ;........... ;......... 5-7 5.3 REACTOR CORE Fuel Assemblies................................................ 5-7 l [ Control Rod Assemblies......................................... 5-7 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature................................ .5-7 - t Vo1ume......................................................... 5 ' 5.5 fuel STORAGE Criticality.................................................... 5-8 LIMERICK - UNIT 1 xxiv 9010300154 901o19 PDR ADOCK 05000332 L- -i P PDC A

1 ~ .I_!!D. fl. c DESIGN FEATURES r L SECTION PAGE-5.1 SITE Exclusion Area.................................................. 5-1 Figure 5.1.1-1 Exclusion Area........................ 5-2 Low Population Zone............................................. 5-1 Figure 5.1.2-1 Low Population Zone................... 5-3 Maps Defining UNRESIRICTED AREAS and SITE BOUNDARY L for Radioactive Gaseous and Liquid Effluents.......... 5-1 i figure 5.1.3-la Map Defining UNRESIRICTED AREAS for Radioactive Gaseous and Liquid Effluents.............. 5-4 Figur e 5.1.3-lb Hap Defining UNRESTRICTED AREAS for Radioactive Gaseous and Liquid Effluents.............. 5-5 (Deleted)....................................................... 5-1 The figure on page 5-6 has been intentionally omitted. Ref er to note on page 5-6................... 5-6 5.2 CONTAINMENT i. Configuration................................................... 5-1 De sign Temperature and Pres sure................................. 5-l' r Secondary Containment......................................';..T.' " 5 '7 "" ~ ~ " ~ " t 5.3 REACTOR CORE fuel Assemblies................................................ 5-7 ]; Control Rod' Assemblies......................................... 5-7 5.4' REACTOR-COOLANT SYSTEM F Design Pressure and Temperature................................ 5-7_ Vo1ume......................................................... 5-8 I 5.5 FUEL STORAGE, Criticality.................................................... 5-8 g LIMERICK-UNITf2 xxiv L I ) tm

I. L DE'flNITIONS REFUELINGFLOORSECONDARYCONTAINMENTINTEGRITY(Continued) b. All refueling floor secondary containment hatches and blowout panels are { closed and scaled. c. The standby gas treatment system is in compliance with the requirements of Specification 3,6.5.3. d. At least one door in each access to the refueling floor secondary containment is closed. The sealing mechanism associat d with each refueling floor secondary e. containment penetration, e.g., welds, bellows, or 0-rings, is OPERABLE. f. The pressure within the refueling floor secondary containment is less than or equal to the value required by Specification 4.6.5.1.2a. REPORTABLE EVENT 1.36 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. R0D DENSITY 1.37 ROD OfNSITY shall be the number of control rod notches inserted as a fraction of the total number of control rod notches. All rods fully _ inserted is equivalent to 100% ROD DENSITY. SHUTDOWN MARGIN -1.38 SHUTDOWN MARGIN shall be the amount of reactivity by which the reactor is o subtritical or would be subcritical assuming all control rods are fully inserted except for the single control rod'of highest reactivity worth which is assumed to be fully wjthdrawn and the reactor is in the shutdown" ^ " ~ e condition; cold, i.e. 68 ft and xenon free. . SITE BOUNDARY-1.39' :The SITE BOUNDARY shall'be that line as defined in figure 5.1.3-la, c 1!40 .(Deleted)- i SOURCE CHECK -1.41 A: SOURCE CHECK shall be-the qualitative assessment of channel response whenL the channel' sensor is exposed to a radioactive source. LIMERICK - UNIT 1-1-7 .e i I,i

_ DEFINITIONS REFUELINGFLOORSECONDARYCONTAINMENTINTEGRITY(Continued) b. All refueling floor secondary containment hatches and blowout panels are closed and scaled. c. The standby gas treatment system is in compliance with the requirements of Specification 3.6.5.3. d. At least one door in each access to the refueling floor secondary containment is closed. e. The scaling mechanism associated with each refueling floor secondary containment penetration, e.g., welds, bellows, or 0-rings, is OPERABLE. f. The pressure within the refueling floor secondary containment is less than or equal to the value required by Specification 4.6.5.1.2a.. REPORTABLE EVENT i 1.36 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. R00 DENSITY i l'.37 R00 DENSITY shall be the number of control rod notches inserted as a fraction i of the total number of control rod notches. All rods fully. inserted is equivalent to 100% ROD DENSITY. i SHUTDOWN MARGIN 1.38 SHUTOOWN M'ARGIN shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming all control rods are fully _ ~ ~ L" inserted except for the single control rod of highest reactivity worth which isassumed.tobefullywfthdrawnand.thereactorisinthe: shutdown " ~ ~ ~ ' condition; cold, i.e. 68 F; and xenon free. SITE 80VHDARY.- -1.39 The SITE B0VHDARY shall be that'line as defined in Figure 5.1.3-la.- i = G 1.40-(Deleted) [ e [ SOURCE CHECK c 1 L 1.41 A' SOURCE CHECK'shall be the qualitative assessment of channel response when l the channel sensor-is exposed to a radioactive source. f-L. - r I 't . LIMERICK. UNIT 2 1-7 t

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Section 3/4 11 3 and _Section 3/4 11.4 (Deleted) '

. o i 4 it i'- L p i THE INf0f.MATION FROM THESE TECHNICAL SPECIFICATIONS SECTIONS HAS BEEN i RELOCAT2D TO THE PCP OR ODCM. TECHNICAL SPECIFICATIONS PAGES 3/4 11-19 THROUGH 3/4 11-20 Of THESE SECTIONS HAVE BEEN INTR.NTIONALLY. 0MITTED. 1 j,s .v 1 04 $I o t' -t -J' t '. LIMERICK-UNIT:b 3/4 11. f,,

W i. t 'i ecdon 3/4 fl.3 through 3/411.4 (Deleted) l 5 l n g i v t Lt t i t i i L:' e N . i--. i 4 .1 i ( THE-INFORMATION FROM THESE TECHNICAL SPECIFICATIONS SECTIONS HAS BEEN RELOCATED-() p.. 10 THE PCP.OR ODCM. TECHNICAL SPECIFICATIONS-PAGES 3/4!11-19-THROUGH 3/4 11-20 0F--THESE: SECTIONS HAVE BEEN INTENTIONALLY OMITTED.

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. ~. RADIDACTIVE EFFLUENTS l BASES-V ..; a 7"- I 3/4.11.?,6 MAIN CONDENSER Restricting the gross radioactivity rate of noble gases from the main condenser F provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment. This specification implements the requirements of

General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50.

3/411.2.7.3/411.3,and3/411.4(Deleted)-INFORMATIONFROMTHESESECTIONS y RELOCATED TO THE ODCM OR PCP. 5 i e f f t' L 3 b i I t 1 + 'p s h (ii; ! LIMERICK - UNIT 1 B 3/4 11 i-f,,r _

N 'ITTwrRr5 EASES 3/4.11.2.6 MAIN CONDENSER Restricting the gross radioactivity rate of noble gases from the main condenser provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CfR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment. This specification implements the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR.Part 50. 3/4.11.2.7,3/4.11.3,and3/4.11.4(Deleted)-INFORMATIONFROMTHESESECTIONSRELOCATED TO THE ODCM OR PCP. i ,a eem,e a s. +4 as. =v. 4 e . LIMERICK - UNIT'2 8 3/4 11-5

4 5;0 DESIGN FEA1URES 5.1 SITE EXCLUSION AREA 5.1.1 The exclusion area shall be as shown in figure 5.1.1-1. LOW P0pULATION 20NE 5.1.2 The low population zone shall be as shown in figure 5.1.2-1. MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR liXiff5XCTWE GX5i50s AND LIQIIIIDTIT0liii3 5.1.3 Information regarding radioactive gaseous and liquid effluents, which will allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE 80VHDARY that are accessible to MEMBER Of Tile pUBLIC, shall be as shown in figures 5.1.3-la and 5.1.3-lb. 5.1.4 (Deleted) c S.2 CONTAINMENT CONFIGURATION 5.2.1 The primary containment is a steel lined reinforced concrete structure consisting of a drywell and suppression chamber. The drywell is a steel-lined reinforced concrete vessel in a shape of a truncated cone on top of a water filled suppression chamber and is separated by a diephragm slab and connected to the suppression chamber through a series of downtomer vents. The drywell has a maximum free air volume of 243,580 cubic feet at a minimum suppression pool level of 22 feet. The suppression chamber has a maximum air region of 159.540 cubic feet and a minimum water region of 122.120 cubic feet. DESI'GN TEMPERATURE AND PRESSURE 5.2.2 The primary containment is designed and shall be maintained for: a. Pa*.imum internal pressure 55 psig. b. 'iximum internal temperature: drywell 340 f. 0 suppression pool 220 f. Maximum external to internal differential pressure 5 psid. c. d.- Maximum floor differential pressure: 30 psid, downward. 20 psid, upward. LIMERICK - UNIT 1 5-1

) r 5.D DESIGN FEATURES 5.1 SITE-i i EXCLUSION AREA j 5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1. LOW POPULATION ZONE 5.1.2 The low population rone shall be as shown in Figure 5.1.2-1. i MAPS DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIDACTIVE GASEOUS AND i L10010 E FLUENTS i 5.1.3 Information regarding radioactive gaseous and liquid effluents, which will i allow identification of structures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBER OF THE PUBLIC, shall be as shown in Figures 5.1.3-la and 5.1.3-lb. 5.1.4'(Deleted) i 5.2 CONTAINMENT I CONF 1GURATION. 5.2.1 The primary containment is a steel lined reinforced concrete structure i i-consisting of a drywell and suppression chamber. The drywell is a steel-lined reinforced concrete vessel in a shape of a truncated cone on top of a water filled suppression chamber and is separated by a diaphragm slab and connected to the suppression chamber through a series of downcomer vents. The drywell.has a maximum free air volume of 243,580 cubic feet at a minimum suppression pool. level i . of 22 feet. The suppression chamber has a maximum air region of 159.540 cubic y -. feet and-a minimum water region of 122,120 cubic feet. ~ ~~ DESIGN TEMPERATURE-AND PRESSt] -~~ .u 1 ll 5.2.2 The: primary containment"is designed and shall be maintained for: l'- a.. Maximum internal pressure 55 psig. c 0

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Maximum internal temperature: drywell 340 F. 0 suppression pool 220 F. ~. ? c. Maximum external to. internal differential pressure 5 psid. I d.~ Maximum floor differential pressure: 30 psid, downward. L 20 psid, upward. i m L:2-

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