ML20247E942

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Proposed Tech Specs Re RCS pressure-temp Limits
ML20247E942
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 05/17/1989
From:
DUKE POWER CO.
To:
Shared Package
ML20247E930 List:
References
NUDOCS 8905260379
Download: ML20247E942 (5)
v • d • e


Text

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        ,:                                                                                                                         -l j74 5 REACTOR COOLANT SYSTEM 3 .//# j #             '

s< 3/4.4.9 PRESSURE / TEMPERATURE LIMITS 9.bf.f& REACTOR C0L/,r4T SYSTEM l LIMITING CONDITION FOR OPER ON 

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_q 3.4.9.1 The Reacto Coolant System.(except the pressurizer) temperature and pressure shall be imited in accordance with the limit lines shown on Figures 3.4 2 end 3.4 3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with: p geS a.g Spec.: Sed k f % M 'S 3 N 4 "J 3' S 3

a. /saximum 1_L..-

heatup of 100 F for Unit 1 and 50 F for Urit 2 ' ry 

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                                    ~la.}es e5 Specified in F sues 3 4-+ and 3 'f- C
b. A [Jnaximum cooldown cf 100 F in any 1-hour p riod, and
c. A maximum temperature change of less than or equal to 10 F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

APPLICABILITY: At all times. ACTION: With any of the above limits exceeded, restore the temperature and/or pressure to within~the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operation or be in at least H0T STANDBY within the next 6 hours and reduce the RCS T and pressure to less than 200 F and 500psig,respectively,withinth8V90llowing30 hours. SURVEILLANCE REQUIREMENTS 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations. 4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, as required by 10 CFR 50, Appendix H in accordance with the schedule in Table 4.4-5. The results of these examinations shall be used to update Figures 3. 4-2)*ad. 3. 4-3, 3 4_. 4, a n d 3, e/- .f. 

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Amendment No.10 (Unit 2) McGUIRE - UNITS 1 and 2 3/4 4-30 Amendment No.29 (Unit 1) 

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j i 2500 i f-Ll: AK TEST LIMITS 2000 1750 6 g UNACCEPTABLE OPE! RATION y 1500 - 0 / m E

a. 1250 O I w

H PRESSU iE-TEMPERATURE LIMITS 6 g 1000 55  ! 750 

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CEPTABLE OPERATION 500 p CRITICALITY Ll MIT BASl!D 2 ON INRP R VICE HYD RnSiATIC TEST TEMPERATURE (32 30F) FOR THE SERVICE PERIC D UP TO 10 EFPY 0 0 50 100 150 200 250 300 350 400 450 INDICATED TEMPERATURE (OF) I CURVE AMLICASLE FOR HEATUP RATES MATERIAL BASIS UP TO 90*F/HR FOR THE SERVICE PERIOO CONTROLLING MATERIAL. WELD METAL UP TO 10 EFPY ANO CONTAINS MARGINS OF COPPER CONTENT.-C.30wt% l 0 10 F AND 80 PSIG FOR POSSISLE l INSTRUMENT ERRORS. PHOSPHORUS CONTENT-0.013wt% ny T INITIAL.C'F RT WT AFTER 10 EFPY 1/4T,178'F 3/4 T,83*F FIGURE 3.4-2 MCGUIRE UNIT 1 REACTOR COOLANT SYSTEM, HEATUk LIMITATIONS l NRC RG 1.99 REV 2 APPLICABLE FOR THE FIRST 10 EFPY l

250C INSE 4VICE LEAK TEST MINI l dVM TEMPEltATURE gl 2250-i I I I 2000  : i I 6 l I 175C tu 5 I h 1500 [ UNACCE TABLE OPE 4ATION 1250-5 o E eResSusie-TEMPERATURE LIMIT / 1000 7% , ACCEPTABLE OPER ATION 5@ 

                                                                                *-- CRITICALITY LIMIT CRITICALITY LlMIT BASE D 250                           SN INRFRVid HYDROSTATIC TEST TEMPE R ATURE (2200F)

FOR THE SEltVICE PERIOD JP TO 8 EFPY  : 0 , O 50 100 150 200 250 300 INDICATED TEMPERATURE (OF) Curves APPLICASLE FOR HEATUP MATE RI AL BASIS RATES UP 70 es*P/HR POR THE CONTROLLING MATERIAL-REACTOR SERVICE PERpOO UP TO O EPPY yEgBEL INTERMEDIATE SHELL 06 AND CONTA1888 MARGINS OF COPPER CONTENT 0.19wt% l io*P ANO so Pese PoM PossasLE RTfdDT INITIAL-4*P INSTRUMENT ERRORS. AFTER R EPPY 1/4T,95'P RTNOT 3/4T,30*P FIGURE 3.4-3 McGUIRE UNIT 2 REACTOR COOLANT l SYSTEM, HEATUk LIMITATIONS i APPLICABLE FOR THE FIRST S EFPY l J

f 2500 1 2250-l 2000-PRESSU RE-TEMPERATUR E LIMIT. 1750 l 3 E 

                                                            ;      1500                                                            g m

o 

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1250-UNACCEPTABLE OP ERATION S w 6 1000 5 750 

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COOLDOWN RATES F/HR , j 500 0-MC 60 " ACCEPTAB LE OPERAT .ON - 250-0 , 0 50 100 150 200 250 300 350 400 INDICATED TEMPE RATURE (OF) CURVES APPLICABLE FOR COOLDOWN RATES MATERIAL BASIS UP TO 80*F/HR FOR THE SERVICE PERIOO CONTROLLING MATERIAL WELD METAL UP TO 10 EFPY AND CONTAINS MARGINS OF COPPER CONTENT-C.30wt% 10*F AND 00 PSIG FOR POSSIBLE PHOSPHORUS CONTENT 0.013wt% INSTRUMENT ERROR. RTNOT INITIAL- 0*F RTNOT AFTER 10 EFPY 1/4T.178*F 3/4T,83*F FIGURE 3.44 McGUIRE UNIT 1 REACTOR COOLANT SYSTEM, COOLD6WN LIMITATIONS, NRC RG 1.99 REV 2 APPLICABLE FOR THE FIRST 10 EFPY 

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l 2500 .

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                           -2250 L

i 2000- ,. G . U' UNACCEPTABLE OPERATIOh , f g  ! 

                    -       1750 s-un      1500 E                                   PRESSURE-TEMPERATURE LIMIT s O
                    $       1250 6

a. E 1000-motnnWN R ATE 750 OF/H R V ACCEPTABLE OF'ERATION O/ , 500 20/ 60 250 

                              .0 0                   50       100         150         200              250        300 3.

INDICATED TEMPERATURE (OF) CURYSS APPLICASLS POR 000LDOWN RATES MATE RIAL SAS88 LP TO SS*P/HR POR THE SERVICE PERIOD CONTROLLING MATERIAL-REACTOR LK' TO 8 EPPY Afe CONTAfMS MARGINS OP VESSEL INTERMEDIATE SHELL OS IS*P AND SS P900 POR POSS40LE COPPER CONTENT--0.19wt% INSTRUMSNT ERRO48. RTNOT INITIAL--4*f P APTER S EPPY 1/4T,SS*P RTNOT 3/47,38'P FIGURE 3.4-5 MCGUIRE UNIT 2 REACTOR COOLANT SYSTEM,COOLDDWN LIMITATIONS APPLICABLE FOR THE FIRST 8 EFPY a..__=-_______-______.--___________}}

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