ML20151Z472

Proposed Tech Specs Revising Table 4.4.6.1.3-1,re Withdrawal Schedule for Reactor Pressure Vessel Matl Surveillance Program Capsules

ML20151Z472
Person / Time
Site:	Limerick
Issue date:	09/14/1998
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20151Z456	List: ML20151Z454 ML20151Z472 ML20151Z488
References
NUDOCS 9809210348
Download: ML20151Z472 (6)

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ATTACHMENT 2 l l

I LIMERICK GENERATING STATION UNIT 2 DOCKET NO. 50-353 LICENSE NO. NPF-85 TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 98-04-2  ;

I LIST OF AFFECTED PAGES  ;

l UNIT 2 3/4 419 3/4 4-21 l

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l 9809210348 900914 PDR ADOCK 05000353 P PDR ,

REACTOR COOLANT SYS_Tf3

, SURVEILLANCE RE0VIREMENTS (Continued) 1 4.4.6.1.2 The reactor coolant system temperature and pressure shall b7 determined to be to the right of the criticality limit line of Figure 2.4.6.1-1 i

curve C and curve C' within 15 minutes prior to the withdrawal of control rods to  !

bring the reactor to criticality and at least once per 30 minutes during system '

heatup. I 4.4.6.1.3 The reactor vessel material surveillance specimens shall be removed and examined, to determine changes in reactor pressure vessel material properties, i

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as required by 10 CFR Part 50, Appendix H in accordance with the schedule in l Table 4.4.6.1.3-1. The results of these examinations shall be used to update the curves of Figure 3.4.6.1-1.

4.4.6.1.4 The reactor flux wire specimens located within the surveillance capsules shall be removed and examined to determine reactor pressure vessel fluence as a function of time and power level and used to modify Figure B 3/4 4.6-1 in accordance with the schedule in Table 4.4.6.1.3-1. The results of these fluence determinations shall be used to adjust the curves of Figure 3.4.6.1-1, as required.

4.4.6.1.5 The reactor vessel flange and head flange temperature shall be verified to be greater than or equal to 70*F:

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a. In OPERATIGNAL CONDITION 4 when reactor coolant system temperature is:

1. s 100*F, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

2. s 90 F, at least once per 30 minutes,

b. Within 30 minutes prior to and at least once per 30 minutes during tensioning of the reactor vessel head bolting studs.

4 LIMERICK - UNIT 2 3/4 4-19

G10 Y16 N24 , g e.p g.a.cus , ,

ECR LG 98-01858 10CFR50.59 l l

N SQQLMfT SYSTEM LGS UNIT 2 Rsvisiin 0 SURVEILLANCE REQUIREMENTS (Continuee) Page 21 of 27 4.4.6.1.2 The mactor coolant systaa temperature and pressum shall be determined ta be to the right of the criticality limit line of Figure 3.4.6.1-1 curves C and c' within 15 ministas prior to the withdrawal of centrol roos to bring the reactor to criticality and at least once per 30 minutas auring systas l heatuo. l 4.4.6.1.3 The reactar vessel material surveillance specimens shall be removed l ano azamined, to datarmine changes in reactor pressure vessel material properties, - l as' required by 10 CFR Part 50, Appendix H in accordanca with the senedule in Table 4.4. 6.1.3-1. The results of these examinat4=a= ahm 11 h. us.w + - ---+.

the curves of Figum 3.4.6.1-1. I Locavsro Capsus a swrrusa Tws sudarrua.act} Asc 4.4.6.1.4 The reactor flux wire specimens s S: " = r: [x " ; F euhage.and amanined ta determine macter pmssum vesse', T,ance as a function of time and power level and used to modify Figure B 3/4 4.5-in The results of these fluence determinations shall be uses ta adjust the curves i f F4 aure 14. 6.1 as required. *=a 6.ao"w wm4 NE j scaneous.e i.4 rbs.a 'e84.1.M -

4.4.6.1.5 The m actor vessel flance and head flange tasper . m.W:4 ^*

to te greater than or equal to 7D*F:

a. In OPERATIONAL-CONDIT5DN 4 when mactar coolant system temperatum is:

1. i 100'F, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

2. 1 SD*F, at least once per 30 minutes.

b. Within 30 minutes prior to and at least once per 30 minutas during tensioning of the reactor. vessel head bolting studs. .

LIMERICK - UNIT 2 3/4 4-19, W25 W I

08/24/98 MON 12:49 [TI/RX NO 61961 @ 024

TABLE 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM-WITHDRAWAL SCHEDULE C

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CAPSULE NUMBER VESSEL LOCATION LEAD FACTOR

• WITHDRAWAL TIME (EFPY) i

[ 131C 7717 G003 30' l.20 15 l z

Z 131C 7717 G002 120' l.20 30 l_

w j 131C 7717 G001 300* 1.20 Spare i

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! 'ECA LG 98 01858 10CFR50.59 Pag) 24

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i ATTACHMENT 3 l l

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1 LIMERICK GENERATING STATION UNIT 2

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I DOCKET NO. 50-353 LICENSE NO. NPF-85 TECHNICAL SPECIFICATIONS CHANGE REQUEST  ;

i NO. 98-04-2 GE Report GE-NE-B1100786-02 '

l " SURVEILLANCE SPECIMEN PROGRAM EVALUATION FOR LIMERICK GENERATING STATION UNIT 2" dated June 1998 l

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