ML20154R658
| ML20154R658 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/21/1986 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20154R655 | List: |
| References | |
| 1438K, NUDOCS 8603310126 | |
| Download: ML20154R658 (11) | |
Text
{{#Wiki_filter:1 l ATTAC W B PROPOSED CHANGE TO APPENDIX A TECHNICAL SPECIFICATION TO OPERATING LICENSE ! NPF-11
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Revised Panes: VI 3/4 2-4 XIX (Revised) 3/4 2-5 , 2-1 3/4 2-6 ) B 2-1 3/4 3-39 l B 2-4 3/4 4-1 (Revised) l B 2-5 . Insert to page 3/4 4-1 B 2-6 3/4 4-la (Revised) B 2-7 Insert to page 3/4 4-la i 3/4 2-1 3/4 4-4a (new page)(delete) 3/4 2-2 3/4 4-4b (new page)(revised) 3/4 2-2(a) (new page) new Figure 3.4.1.5.1 B 3/4 4-1 , Insert behind B 3/4 4-1 l l l 8603310126 860321 DR ADOCK 0 3 1438K
INDEX ' LIST OF FIGURES FIGURE PAGE 3.1.5-1 i SODIUM PENTA 80 RATE SOLUTION TEMPERATURE / CONCENTRATION REQUIREMENTS ............................. 3/4 1-21 3.1.5-2 l 500IUM PENTA 80 RATE (Na2 8t o0t s
- 10 H 2O) l VOLUME / CONCENTRATION REQUIREMENTS ...................... 3/4 1-22 3.2.1-1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, ,
l INITIAL CORE FUEL TYPiS 002 0'Il B 00%711 . . . . . . . . . . . . . . . . . . . 100, 000020, MO 3cRB l%, RCR8 21% MD ICR !
............................. 3/4 2-2 t 3.2.3-1 MINIMUM CRITICAL POWER RATIO (MCPR) VERSUS t AT' RATED FLOW ........................................ 3/4 2-5 3.2.3-2 K 7 FACTOR .............................................. 3/4 2-6 3.4.6.1-1 MINIMUM REACTOR VESSEL METAL TEMPERATURE VS. REACTOR VESSEL PRESSURE ............................ 3/4 4-18 4.7-1 1 SAMPLE PLAN 2) FOR SNUB 8ER FUNCTIONAL TEST3/4 .............
7-32 B 3/4 3-1 { REACTOR VESSEL WATER LEVEL ............................. B 3/4 3-7 8 3/4.4.6-1 CALCULATED FAST NEUTRON FLUENCE (E>1MeV at 1/4 AS A FUNCTION OF SERVICE LIFE ..........)........T........ . B 3/4 4-7 5.1.1-1 EXCLUSION AREA AND SITE BOUNDARY FOR AND LIQUID EFFLUENTS . . . . ................... . . . . . . . . . . . . GASEOUS 5-2 5.1.2-1 LOW POPULATION ZONE .................................... 5-3 6.1-1 CORPORATE MANAGEMENT ................................... 6-11 6.1-2 UNIT ORGANIZATION ...................................... 5-12 6.1-3 MINIMUM SHIFT CREW COMPOSITION ......................... 6-13 3.2.1-2 l MArlMitM AVERAGE Pt.SNAR LWEAR HEAT GENERATION KATE (MAPLHGR) VERsus AVERAGE PLANAR EXPOSURE, FdEL TYPE BP8cR 8299 L' r m 3/42 -2 (c-) 3.4.1.1 - 1 CORE THERM A L ' POWER - __ }b TOTAL CORE FLOW (% of RATED) (% OFRATED) VERsues 3N 4-Ib - LA SALLE - UNIT 1 XIX Amendment No.'ll
3/4.4 REACTOR COOLANT SYSTEM
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3/4.4.1 RECIRCULATiONSYSTEM RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION 3.4.1.1 Two reactor coolant system recirculation loops shall be in operation. APPLICABILITY: OPERATIONAL CONDITIONS 1* and 2*. ACTION:
- a. With one reactor cr.,olant system recirculation loop not in operation:
"1. Within 4 hours:
a) Place the recirculation flow control syste's in the Master Manual mode, and t) "ed.;a " *L".".L POSE.i t: j, 5"*' Of P.^.TED "EP".".L POSER , =d , Qg Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Safety Limit by 0.01 to 447-per Specification 2.1.2, and, *
- i. o8. ' m Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Limiting c) M' Condition for Operation by 0.01 per Specification 3.2.3, and, Reduce the MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE chm -(MAPLHGR) limit to a value of 0.85 ti:nes the two recirculation loop operation limit per Specification 3.2.1, and, e)ff Reduce the Average Power Range Monitor (APRM) Scram and Rod Block and Rod Block Monitor Trip Setpoints and Allowable Values to those applicable.to single loop recirculation Insert loop operation per Specifications 2.2.1, 3.2.2, and 3.3.6.
following ,
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W that the APRM flux noise averaged over utes a) does not 5% peak to peak; othe m , educe the recirculation lo flux naise is less than the 5% peak to p'en w unt yand, b). Verify t ., e core plate AP noise doe xceed 1 psi o peak; othe mise, reduce the recirculati flow until the AP noise is less than the 1 psi limit. ._
"See Special Test Exception 3.10.4.
LA SALLE - UNIT 1 3/4 4-1 Amendment No.18
Following paga 3 4-1:
- 2. When operating within the surveillance region specified in Figure 3.4.1.1-1:
- a. With core flow less than 39% of rated core flow, initiate action within 15 minutes to either:
- 1. Leave the surveillance region within 4 hours, or
- 2. Increase core flow to greater than or equal to 39% of rated I flow within 4 hours.
- b. With the APRM add LPRM# neutron flux noise level greater than three (3) times-their established baseline noise levels: ,
- 1. Initiate corrective action within 15 minutes to restore the noise levels to within the required limit within 2 hours, otherwise
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- 2. Leave the surveillance region specified in Figure 3.4.1.1-1 i
within the next 2 hours. 3 i, I s j # - Detector levels A and C of one LPRM string per core octant plus detector i' levels A and C of one LPRM string in the center region of the core should be monitored. I f
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8 k, . s REACTOR COOLANT SYSTEM , LIMITING CONDITION FOR OPERATION (Continued) ACTION: (Continued) uoZ 7 3. The provisions of Specification 3.0.4 are not applicable, wag 3 -?
- 4. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours.
- b. With no ' reactor coolant system recirculation loops in operation, 4 immediately initiate measures to place the unit in at least HOT ~
SHUT 00WN within the next 6 hours. , ! I I l SURVEILLANCE REOUIREMENTS _ 4.4.1.1 Each reactor coolant system recirculation loop flow control valve shall be demonstrated OPERABLE at least once per 18 months by:
- a. Verifying that the control valve fails."as is" on loss of hydraulic 4
pressure at the hydraulic power units, and
- b. Verifying that the average rate of control valve movement is: -
- 1. Less than or equal to 11% of stroke per second opening, and
- 2. Less than or equal to 11% of stroke per second closing.
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follodng P"9e LA SALLE - UNIT. 1 3/4 4-la Amendment No. 18
. . . . . _ . _ , . _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ __.. _ .-- _ _., _ - _ _ _ _ ~ _ __. ___.__ _ _. _._ _ .. __.
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Following pugn 3/4 4-la: l I
- 4.4.1.2 With one reactor coolant system recirculation loop not in operation:
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- a. Establish baseline APRM and LPRM# neutron flux. noise level )
i values within 4 hours upon entering the surveillance region of Figure 3.4.1.1-1 provided that baseline values have not been established since last refueling. I { b. When operating in the surveillance region of Figure
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3.4.1.1-1, verify that the APRM and 1.PRM# neutron flux
! noise levels are less than or equal to three (3) times the baseline values:
l l 1. At least once per 12 hours, and i l 2. Within 1 hour after completion of a THERMAL POWER , I increase of at'least 5% of RATED THERMAL POWER, ! l initiating the surveillance within 15 minutes of l completion of the increase. l '
- c. When operating in the surveillance region of Figure 3.4.1.1-1, verify that core flow is greater than or equal to ;
l 39% of rated core flow at least once per 12 hours. , l I ( 4 1
# - Detector levels A and C of one LPRM string per core octant plus detector levels A and C of one LPRM string in the center region of the core should be monitored.
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r-l The possibility of thermal hydraulic instability in a BWR has been investigated since the startup of early BWRs. Based on tests and analytical models .it has been identified that the high power-low flow corner of the power-to-flow map is the region of least stability margin. This region maybe encountered during startups, shutdowns, sequence exchanges, and as a result of a recirculation pump (s) trip event. To ensure stability, single loop operation is limited in a designated restricted region ~(Figure 3.4.1.1-1) of the power-to-flow map. Single loop operation with a designated surveillance region (Figure 3.4.1.1-1) of the power-to-flow map requires monitoring of APRM and LPRM noise levels. I l
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l l l i Insert Following Page B 3/4 4-1 l 1438K l
SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated the proposed Technical Specification Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated because:
For Cycle 2, the MCPR fuel cladding integrity safety limit was changed from 1.06 to 1.07 for two recirculation loop operation, and from 1.07 to 1.08 for single recirculation loop operation. The safety limit is smaller for initial cores because the uncertainties in TIP readings'and the R Factor are smaller. The addition of a new MAPLHGR 'vs Exposure curve for the reload fuel type BP8CRB299L in the APLHGR Technical Specification. The MAPLHGR limits were provided by General Electric in the Supplemental Reload Licensing Submittal LIC2. The replacement of the existing MCPR curve with a revised curve which j reflects the limiting transients for cycle 2. The MCPR limits were ' provided by General Electric in the Supplemental Reload Licensing l Submitting LIC2. Although the cycle specific demonstrated adequate i stability, single loop thermal hydraulic stability requirements were I added to the Recirculation System Technical Specification to address the NRC concerns in this area.
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated because: ,
l The proposed Technical Specification changes do not represent significant changes in acceptance criteria or safety margins and all changes have been made based on methods that have been previously accepted by the NRC. -The reload core involves a new fuel type which must be licensed. The new fuel type has been analyzed with approved methods and meets the approved limits of GESTAR. The new fuel type presents no unreviewed safety questions because the bundle design has been approved by the NRC, and licensing of new bundle enrichments has been treated as a non-safety related change to GESTAR.
- 3) Involve a significant reduction in the margin of safety because:
The deletion of the EOC-RPT inoperable provision in the MCPR and EOC Recirculation Pump Trip System Technical Specifications. The EOC-RPT inoperable analysis was .not justified in the second cycle but may be included in future cycles. The replacement of the existing Kg curve with a revised curve which is based on LaSa11e's rated core power and core flow. The original curve ; was a generic curve. l Based on the preceding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria-with respect to the system or component, the consequences of previously evaluated accidents will not be increased and the mursin of safety will not be decreased. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CFR 50.92, the proposed change does not l constitute a significant-hazards consideration. f 1438K}}