ML20044G772
| ML20044G772 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 05/27/1993 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20044G583 | List: |
| References | |
| NA-93-0131, NA-93-131, NUDOCS 9306040239 | |
| Download: ML20044G772 (15) | |
Text
.
Attachment IV to NA 93-0131 Page 1 of 15 ,
A**-u-. ,
Attachment IV i Proposed Technical specification Changes A
9306040239 PDR 930528 P
ADOCK 050004B2 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 VALVES .......................................... 3/4 4-21 CHEMISTRY ...........................................
3/4 4-22 3/4.4.7 TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS ............. 3/4 4-2 TABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY SURVEILLANCE REQUIREMENTS .................................... 3/4 4-24 3/4.4.8 SPECIFIC ACTIVITY ................................... 3/4 4-25 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 TABLE 4.4-5 D DELETED Pressurizer .....................................
3/4 4-33 Overpressure Protection Systems ................. 3/4 4-34 FIGURE 3.4-4 MAXIMUM ALLOWED PORY SETPOINT FOR THE COLD 3/4 4-36 OVERPRESSURE MITIGATION SYSTEM ..................
3/4.4.10 STRUCTURAL INTEGRITY ................................ ')/4 4-37 REACTOR COOLANT SYSTEM VENTS ........................ 3/4 4-38 3/4.4.11 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS ........................................ 3/4 5-1 VIII Amendment No. 44,57 WOLF CREEK - UNIT 1
. - . . .. - - . . - - - . - . . . ~
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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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~
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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
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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
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Attachment IV to NA 93-0131- t Page'7 of 15 4 f 4 4 5 5 INSERT B REVISED FIGURE 3.4-3
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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
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Attachment IV to NA 93-0131 Ya 9 of 15 tusgitr ( 3000
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. . . . - - . . -. .. -_ -.= -,. ---. . .-.... - - _ .
- Attachment IV to-NA 93-0131 ;
Page 10 of 15- .) i i
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' Attachment IV to NA 93-0131
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t 7 ... 0 100 200 300 400 500 MEASURED RTD TEMPERATURE (DEG. F)
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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 p PRESSURE / TEMPERATURE LIMITS (Continued)
- 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. l Heatup and cooldown limit curves are calculated using the most limiting value 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 ! chosen such that the limiting RTNDT at the 1/4T location in the core region is 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 determineReactortheir initial RT NDT; the results of these tests are shown in Table B 3/4.4-1. 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 RTEDT at the end of-}-EF Y as well as adjustments for possible errors in the pressure and temperature sing instruments. N B 3/4 4-7 Amendment No. 40 WOLF CREEK - UNIT 1
Attachment IV to MA 93-0131 Page 13 of 15 sasaeT D
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CE I 1/4T 1.3 X 10 U n/c=2 0' -
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I I I I I I ' I 10 " 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
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, 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
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Attachment IV to NA 93-0131 Page 15 o*f 15 10 _ T INNER SURFACE
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e : z : O D _I w 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
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