Text

Proposed Tech Specs 3/4.4.9.1,pressure/temp Limits RCS & 3/4.4.9.3,overpressure Protection Sys
	ML20044G772
Person / Time
Site:	Wolf Creek
Issue date:	05/27/1993
From:	; WOLF CREEK NUCLEAR OPERATING CORP.
To:	;
Shared Package
ML20044G583	List: ML20044G582; ML20044G772;
References
	NA-93-0131, NA-93-131, NUDOCS 9306040239
	Download: ML20044G772 (15)
	v • d • e

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Attachment IV to NA 93-0131 Page 1 of 15 A**-u-.

Attachment IV i

Proposed Technical specification Changes A

9306040239 930528 PDR ADOCK 050004B2 P

PDR i

i

' Attachment IV to NA 93-0131 Page 2 of 15 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS E.ME SECTION TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION 3/4 4-21 VALVES..........................................

3/4 4-22 3/4.4.7 CHEMISTRY...........................................

TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS............. 3/4 4-2 TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY SURVEILLANCE 3/4 4-24 REQUIREMENTS....................................

3/4 4-25 3/4.4.8 SPECIFIC ACTIVITY...................................

FIGURE 3.4-1 DOSE EQUIVALENT I-131 REACTOR COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY

> 1 pCi/ GRAM DOSE EQUIVALENT I-131..............

3/4 4-27 TABLE 4.4-4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM................................

3/4 4-28 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Re actor Cool ant System..........................

3/4 4-29 FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS 3/4 4-30 APPLICABLE UP T0 +

FIGURE 3.4-3 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS APPLICABLE UP T0 + EFPY......................... 3/4 4-31 D

DELETED TABLE 4.4-5 3/4 4-33 Pressurizer.....................................

Overpressure Protection Systems................. 3/4 4-34 FIGURE 3.4-4 MAXIMUM ALLOWED PORY SETPOINT FOR THE COLD OVERPRESSURE MITIGATION SYSTEM..................

3/4 4-36 3/4.4.10 STRUCTURAL INTEGRITY................................ ')/4 4-37 3/4.4.11 REACTOR COOLANT SYSTEM VENTS........................

3/4 4-38 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4 5-1 3/4.5.1 ACCUMULATORS........................................

WOLF CREEK - UNIT 1 VIII Amendment No. 44,57

.. ~

Attachment IV to NA 93-0131 e 3 of 15

, f-MATER:AL PitO*ERTY BASIS Controlling Material-RV Lower Shell Copper Content:

0.07 we ht s Nickel Content:

0.62 We ht s initic! RT 40 Dog

~

NDT RT After 7 EFPY:

1/4T: 108.0 Dog F NOT 3/4T: 99.47 Dog F

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l .'li 1000 f f r / x l ,i i / / / \\ l I i ltli f /' dI i N 'li! u I, v i / N i t j / -r 500 m!TICALITh!h!T GW .;g g / IISOvlCI @TATIC TUT j ',I' l' / TDrtRATWE (taff) PIR TIE - ~ m l ' / I s a vict psal m w\\ e F EF M t / e e / I O f f O 1 200 300 400 500 l ' INDICATED TEMPERATURE (DEG. F) l FIGURE 3.4-2 \\ REACTOR COOLANT SYSTEM HEATUP LIMITATIONS-APPLICA8LE UP T0 7 EFPY WOLF CREEK - UNIT 1 3/4 4-30 Amendment No. 40 i

. Attachment IV to NA 93-0131~ Rage.4 of:15 a 4 h e P 9 'I b T 'r INSERT'A t REVISED' FIGURE 3.4-2 P .I i t i ? -t 1 h ,b .:.s l I -) l '1 l

Attachment IV to NA 93-0131 Page,5 of 15 MATERIAL PROPERTY BASIS Controlling Material: RV Lower Shell Copper Content: 0.07 Weight % Nickel Content: 0.62 Weight % Initial RTNDT: 40*F Limiting ART after 13.6 EFPY: 1/4T,89 'F 3/4T, 79

F 3,000 1

.u..a .... o. L a.--.,. 4 i CRITICALITY LIMIT . -.4 - BASED ON 60*F/HR. j. L.;. ,.,.y ._.e ,_ HEATUP CURVE L.,. 2. 4/2 E! L + ' + + r 2,500 ,.. 2 LEAK TEST LIMIT .1-- ,. _...,.4...,1 . i.! ~ .. a ,.4_, . - + -. . } W-y : lQ j y 2,000 .,_._..g.4 r g i i, _.4_.., 2.j..,,,a _; 1 .a.__., m. w ,~! Of r a ,._,_,.t --) u) CRITICALITY LIMIT ^~ ^ u) BASED ON 100'F/HR!. @ 1,500

60 'F/HR T-

. ; HEATUP CURVE U_..u c., - HEATUP CURVE - .4 O ~.. w k i. 2. , 2.,_._, o._ @ 1,000 j i _; _. g -r-. ~ 4 _.. i t .7 CRITICALITY LIMIT 4 ~ ~ BASED ON INSERVICE i~~"~ ~~ ; HYDROSTATIC TEST 500 - ' - 100 'F/HR TEMPERATURE (222*F) - - +* HEATUP CURVE : o FOR THE SERVICE .H 4 ++ PERIOD UP TO 13.6 EFPY _l.. :...D, : ;.. w....... I i ;';i' . 'i ii'! I' o o 100 200 300 400 500 ) INDICATED TEMPERATURE (DEG. F) 4 l FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS APPLICABLE UP TO 13.6 EFPY l

Attachment IV to NA 93-0131 Page 6 of 15 m ( /A/stiili-8 V MATERAL PROPERTY IMS15 Controlling Meteriel: RV Lower Shell Copper Content: 0.07 Wei ht s Nickel Content: 0.62 We ht s initial RT 40 Dog NDT RT After 7 EFPY: 1/4T: 108.0 Dog F NDT 3/4T: 99.47 Dog F / / 3000 t illi N iil i l l l i l l i l l l i l l ! I l l i l l l i l i l l l/ 1111!' ..Ni,

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1 I ' / I1 s / s \\ I 0 0 100 200 300 400 500 INDICATED TEMPERATURE (DEG. F) i FIGURE 3.4-3 REACTOR COOLANT SYSTEM C00LDOWN LIMITATIONS APPLICABLE UP TO 7 EFPY WOLF CREEK - UNIT 1 3/4 4-31 Amendment No. 40

Attachment IV to NA 93-0131-t Page'7 of 15 4 f 4 4 5 5 INSERT B REVISED FIGURE 3.4-3 ? ~ t 'h i .1 l I i ) i

Attachment IV to NA 93-0131 Page 8 of 15 MATERIAL PROPERTY BASIS Controlling Material: RV Lower Shell Copper Content: 0,07 Weight % Nickel Content: 0.62 Weight % Initial RTNDT: 40*F Limiting ART after 13.6 EFPY: 1/4T, 89

F 3/4T, 79 'F 3,000

. ' ;-, +,, .2., .. _. 2 a. ;.. l ... - i p. , - 4. ...,......4.4... 4 4 2. 4- .l--.. ..l.. 6 i - ~- ", 2,500 - - ~ ' -' - ~~ i 1 L _ +. 4.. ._.u-. + t f n. 1 2 9 2,000 2~ + ' ' 1 u) .-4 g i g r. .. m v 5 6 -.. ....j...'. ..4 D i a..L u) .L. ,-.4..- s._ v) i W 1,500 + e a... .g.._. _ 4_ a t i t h u. ..i-. l t.4 [1] p o 5 COOLDOWN RATES 1,000 ( *F/HR) Z 0 20 40 g 60_in 500 100 + 1 - - - - t -

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4...l. .2 44 4 k I _) I l .~4 - i h r. 44.,e.-~6 ,.-4.-.... n 4 4 4 0 0 100 200 300 400 500 INDICATED TEMPERATURE (DEG. F) FIGURE 3.4-3 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS APPLICABLE UP TO 13.6 EFPY

Attachment IV to NA 93-0131 Ya 9 of 15 tusgitr ( 3000 \\- I lll ll l \\- 2750 - i.i e i si i j / 2500 ( y) (p. g p s7 504 's 127 504 / x177 506 -- 2250 - g m / l 277 644 / 1055 / 1810 2000 x l N: ll! l l,/ g /] [1750d / f ~ l i k

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J t:: k1500 ~ C l } m / / \\ S 1250 - X / 2 / / ~ 1000 l / / s 750 - /' / / j s l .e~ 500 / / 250 - / / 7 / \\ 0 / 0 100 200 300 400 WEASURED RTD TEMPERATURE (DEG. F) FIGURE 3.4-4 MAXIMUM ALLOWED PORY SETPOINT FOR THE COLD OVERPRESSURE MITIGATION SYSTEM WOLF CREEK - UNIT 1 3/4 4-36 Amendment No. 40

-.= -,. ---. - Attachment IV to-NA 93-0131 Page 10 of 15- .) i i -'] 4 I .i l t INSERT C s REVISED FIGURE 3.4-4 I s b .. f i h ? 9 .l i u 5 I -t t J( i I'l f i 8 ? P ,a = v -*g-w v .m-w w e w- -- - - + ~ a

+

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' Attachment IV to NA 93-0131 ,Page 11 of 15 3,000 2.. .._4___...- .. ~ .._4 . - + , ~ - - - - - - ~ ~. 2,750 1 1 +, s n 2,500 -- ~..... _. TRTD PSMAX -4 J .n... . + -..-.,. L - ...m ( 'F) (PSIG) 2,250 ~ - - - - ~ .._.u .g. 2._... 97 485 ...- n 2

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~ ^ - 127 485 ...f ....-..'--.~.i_- 4 ..L 177 485 .-- _ g -.. -.- 7 2,000 227 545 -~ ~ ~ ..E ~ 6 277 745 I' . 1. + 327 1310 g 372 2335 E,750 1 g Z r - - - - - -~ - < - @ 1,500 g g g I $ 1,250 O ~ ~ ^ ~ ~

1,000

~ 750 e. .i m 4 500 ~ 250 , =... - - A.- .4.. e m..-.. 9.=. t 7 0 100 200 300 400 500 MEASURED RTD TEMPERATURE (DEG. F) ') l FIGURE 3.4-4 MAXIMUM ALLOWED PORV SETPOINT FOR THE COLD OVERPRESSURE MITIGATION SYSTEM

Attachment IV to NA 93-0131 Page 12 of 15 REACTOR COOLANT SYSTEM BASES PRESSURE / TEMPERATURE LIMITS (Continued) p b. Figures 3.4-2 and 3.4-3 define limits to assure prevention of non-ductile failure only. For normal operation, other inherent plant characteristics, e.g., pump heat addition and pressurizer heater capacity, may limit the heatup and cooldown rates that can be achieved over certain pressure-temperature ranges. 2. These limit lines shall be calculated periodically using methods provided below. 3. The secondary side of the steam generator must not be pressurized above 200 psig if the temperature of the steam generator is below 70'F. 4. The pressurizer heatup and cooldown rates shall not exceed 100'F/h' and 200'F/h, respectively. The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 583'F. 5. System preservice hydrotests and in-service leak and hydrotests shall be performed at pressures in accordance with the requirements of ASME Builer and Pressure Vessel Code, Section XI. The fracture toughness properties of the ferritic saterials in the reactor vessel are determined in accordance with the 1972 Winter Addenda to Section III of the ASME Boiler and Pressure Vessel Code. Heatup and cooldown limit curves are calculated using the most limiting value l of the nil-ductility reference temperature, RT DT, at the end of eff etive t full power years (EFPY) of service lifbha EFPY service life is at the 1/4T location in the core region is chosen such that the limiting RTNDT of the limiting unirradiated saterial. The selection of greater than the RTNDTassures that all components in the Reactor Coolant System such a limiting RTNDT will be operated conservatively in accordance with applicable Code requirements. The reactor vessel saterials have been tested to determine their initial Reactor NDT; the results of these tests are shown in Table B 3/4.4-1. RT operation and resultant fast neutron (E greater than 1 MeV) irradiation can Therefore, an adjusted reference temperature, l cause an increase in the RTNDT. based upon the fluence and copper content and nickel content of the material in question, can be predicted using Figure B 3/4.4-1 and the largest value of ART c mputed by 'tb Regulatory Guide 1.99, Revision 2, " Radiation NDT Embrittlement of Reactor Vessel Materials." The heatup and cooldown limit curves of Figures 3.4-2 and 3.4-3 include predicted adjustments for this shift in RT at the end of-}-EF Y as well as adjustments for possible errors in EDT the pressure and temperature sing instruments. N WOLF CREEK - UNIT 1 B 3/4 4-7 Amendment No. 40

Attachment IV to MA 93-0131 Page 13 of 15 sasaeT D / I / / ~ INNER SU CE U n/c=2 I 1/4T 1.3 X 10 0' "a ~ 5 ~ ~ 2 c 18 n/c=2 ~ 3 3/47 2.9 X 10 5 =d I, 1s g 10 E [ i = 10 " I I I I I I I O 5 10 15 . ~ 20 25 30 32 35 SERVICE t!FE (EFFECTIVE FULL POWER YEARS) i FIGURE B 3/4.4-1 FAST NEUTRCN FLUENCE (E>1MeV) AS A FUNCTION EFFECTIVE FULL POWER LIFE \\ WOLF CREEK - UNIT 1 B 3/4 4-11 Amendment No. 40

. Attachment IV to NA 93-0231 'l Page 14 of 15 1 6 9 e I -t i i k i i J IMSERT D REVISED FIGURE B 3/4.4-1 t a ~ .e I 1 I I I ? i t

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k i I i-l .6 I t -t e k

Attachment IV to NA 93-0131 Page 15 o*f 15 10 INNER SURFACE T ~ ~ Eo 19 j10 1/4 T 1.88 x 10" o I ~ 3/4 T 6.69 x 10" W ~ Oz 18 $10 e z O _I Dw 17 i z 10 i 10 O 5 10 15 20 25 30 32 35 SERVICE LIFE (EFPY) . FIGU'RE B 3/4.4-1:' FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF.: EFFECTIVE FULL POWER LIFE )}}

ML20044G772

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