ML20054J039

Amend 86 to License DPR-44,revising Tech Specs to Permit Reactor Operation W/Reload Core 5 for Cycle 6

ML20054J039
Person / Time
Site:	Peach Bottom
Issue date:	06/17/1982
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co
Shared Package
ML20054J040	List: ML20054J039 ML20054J041 ML20054J042
References
DPR-44-A-086 NUDOCS 8206280004
Download: ML20054J039 (30)

Text

{{#Wiki_filter:__ 6 /' UNITED STATES PT NUCLEAR REGULATORY COMMISSION o g\\ nj wAsHincrow, p. c. zones k,,N PHILADELPHIA ELECTRIC CO WANY PUBLIC SERVICE ELECTRIC AND GAS COWANY DELPARVA POWER AND LIGHT _CO N ANY ATLANTIC CITY ELECTRIC COWANY DOCXET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 I AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.86 License No. DPR-44 i 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated February 19, 1982, as supplemented June 3,1982, cornplies with the standards and requirements of the Atomic Energy Act of 1954, as emended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; '. The facility will operate in confomity with the application,. B the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the C,ommission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. o 2. Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment c; and paragraph 2.C.(2) df Facility Operating License No. DPR-44 is. ~ hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as reviped through Amendment No. 86, are hereby incorporated in the licensa. PEC0 shall operate the facility in accordance _ with the Technical Specifications. 8206280004 820617 DR ADOCK 05000277 p PDR

f 2-r 3. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGU TORY COMMISSION ^ 60 Jo & F. Stolz, Chief l Op rating Reactors Branch #4 vision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: June 17,1982 l / l

-? ..,,,...nme.---. .=~.m. . ~ ~ ~ ~ - -. - ~ ~ ~ ~ * " - -. - = ~ - . = ~ e - me os ~ ~. * * = -o----, 3 o s ,e i ! ^,, ATTACHMENT T0 LICENSE AMENDMENT NO.86 1 FACILITY OPERATING LICENSE NO. OPR 44 ~ DOCKET NO. 50-277 j Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating'the area of change. Remove Pages Insert Pages iv . iv iva j vi vi 9 9 r 13 13 )l 14 14 103 103 ^ 104 104 133a 133a 133b 133b 133c 133c 133d 133e 140 140 140a 140a L i '140b 140b 140c 140c i 140d 140d 5 140e B f 't. 4 _ i, ! _ -_..

,i i l ! Remove ~Pages Insert Pages 142 142 142a 142a 142b 142b 142c i 142f 142f 142g 142g 142h 142h 1421 142j ~ g o lt t f 9 9 i o e 'i I P

==4

PBAPS Unit 2 i LIST OF FIGURES Figure Title Page l' } 1.1-1 APRM Flow Bias Scram Relationship To 16 1 Normal Operating Conditions f l 4.1.1 Instrument Test Interval Determination 55 t Curves i j 4.2.2 Probability of System Unavailability 98 Vs. Test Interval 3.4.1 Required Volume and Concentration of 122 2 1 Standby Liquid Control System Solution 3.4.2 Required Temperature vs. Concentration 123 for Standby Liquid Control System Solution 3.5.K.1 MCPR Operating Limit vs. Tau 8x8R/LTA 142 l 3.5.K.2 MCPR Operating Limit vs. Tau,P8X8R Fuel 142a 3.5.K.3 MCPR Operating Limit vs. Tau,P8DRB285 Fuel 142b 3.5.1.E Kf Factor Vs. Core Flow 142d 3.5.1.F MAPLHCR Vs. Planar Average Exposure, 142e Unit 2, 8x8 LTA Fuel, 100 mil channels i. 3.5.1.C MAPLHCR Vs. Planar Average Exposure, 142f Unit 2, 8x8R Fuel, Type 8DRB284, 100 mil channels 3.5.1.H MAPLHGR Vs. Planar Average Exposure, 142g Unit 2, P 8X8R Fuel, Type P8DRB285, 100 ml] channels 3.5.1.I MAPLHGR vs. Planar Average Exposure, 142h Unit 2, P'8x8R Fuel, Type P8DRB284 H, 80 mil & 100 mil channel & 120 mil channels 3.5.1.J. MAPLHGR vs. Planar Average Exposure 142i L Unit 2, P8X8R Fuel, Type P8DRB299, 100 mil channels 3.5.1.K. MAPLl!GR vs. Planar Average Exposure 142j Unit 2, P8X8R Fuel (Generic) a r 1 I! l: ll Amendment No. 3%, $@, #5, JB, 7@,86 -iv-ll ll ll

PBAPS Unit 2 LIST OF FIGURES i Figure Title Page 3.6.1 Minimum Temperature for Pressure Tests 164 such as required by Section XI 3.6.2 Minimum Temperature for Mechanical Heatup 164a or Cooldown following Nuclear Shutdown 3.6.3 Minimum Temperature for Core Operation 164b (Criticality) 3.6.4 Transition Temperature Shift vs. Fluence 164c 6.2-3 Management Organization Chart 244 6.2-2 Organization for Conduct of Plant Operation 245 I i 5 Amendment No. 86 - iva-

PBAPS Unit 2 LIST OF TABLES Table Title Page 4.2.B Minimum Test and Calibration Frequency 81 for CSCS 4.2.C Minimum Test and Calibration Frequency 83 for Control Rod Blocks Actuation 4.2.D Minimum Test and Calibration Frequency 84 for Radiation Monitoring Systems 4.2.E Minimum Test and Calibration Frequency 85 for Drywell Leak Detection 4.2.F Minimum Test and Calibration Frequency 86 for Surveillance Instrumentation 4.2.G Minimum Test and Calibration Frequency 88 for Recirculation Pump Trip 133d 3.5.K.2 Operating Limit MCPR Values for Various Core Exposures 133e 3.5.K.3 Operating Limit MCPR Values for Various Core Exposures 4.6.1 In-Service Inspection Program for Peach 150 Bottom Units 2 and 3 3.7.1 Primary Containment Isolation Valves 179 l 3.7.2 Testable Penetrations With Double 184 O-Ring Seal s 3.7.3 Testable Penetrations with Testable 184 Bellows 3.7.4 Primary Containment Testable Isolation 185 Valves 4.8.1 Radioactive Liquid Waste Sampling 210 l and Analysis 4.8.2 Radioactive Gaseous Waste Sampling 211 and Analysis 234d 3.11.D.1 Safety Related Shock Suppressors l' 240k 3.14.C.1 Fire Detectors l -vi-I I Amendment No. 77, f$,86

PBAPS Unit 2 SAFETY LIMIT LIMITING SAFETY SYSTEs* SETTING 1.1 FUEL CLADDINC INTECRITY 2.1 FUEL CLADDING INTEGRITY Applicability: Applicability: The Safety Limits established The Limiting Safety System Settings to preserve the fuel cladding apply to trip settings of the instru-integrity apply to those ments and devices which are provided variables which monitor the to prevent the fuel cladding integrity fuel thermal behavior. Safety Limits from being exceeded. Objectives: Objectives: The objective of the Safety The objective of the Limiting Safety Limits is.to establish limits System Settings is to define the level which assure the integrity of of the process variables at which auto-the fuel cladding. matic protective action is initiated to prevent the fuel cladding integrity Safety Limits from being exceeded. Specification: Specification: A. Reactor pressure 1800 psia The limiting safety system settings and Core Flow 210% of Rated shall be as specified below: A. Neutron Flux Scram The existence of a minimum

1. APRM Flux Scram Trip Setting critical power ratio MCPR (Run Mode) less than 1.07 for two recirculation loop operation, When the Mode Switch is in the or 1.08 for single loop RUN position, the APRM flux operation, sha)) constitute scram trip setting shall be:

violation of the fuel clad-ding integrity safety limit. S< 0.66W + 54%-0.66 A W To ensure that this safety where: limit is not exceeded, neutron flux shall not be above the S = Setting in percent of rated scram setting established in thermal power (3293 MWt) l speci fication 2.1. A for longer than 1.15 seconds as indicated W = Loop recirculating by the process computer. When flow rate in percent the process computer is out of of design.W is 100 for core sorvice this safety limit shall flow of 102.5 million Ib/hr be assumed to be exceeded if or greater. the neutron flux exceeds its scram setting and a control rod r scram does not occur. i Amendment No. 75, JA, M, 48, 78,86 l

PBAPS Unit 2

1.1 BASES

FUEL CLADDING INTEGRITY A. Fuel Cladding Integrity Limit at Reactor Pressure D 800 psia and Core Flow t 10% of Rated The fuel cladding integrity safety limit is set such that no fuel damage is calculated to occur if the limit is not violated. Since the parameters which result in fuel damage are not directly observable during reactor operation the thermal and hydraulic conditions resulting in a departure from nucleate boiling have been used to mark the beginning of the region where fuel damage could occur. Although it is recognized that a departure from nucleate boiling would not necessarily result in damage to BWR fuel rods, the critical power at which boiling transition is calculated to occur has been adopted as a convenient limit. However, the uncertainties in monitoring the core operating state and in the procedure used to calculate the critical power result in an uncertainty in the value of the critical power. Therefore, the fuel cladding integrity safety limit is defined as the critical power ratio in the limiting fuel assembly for which more than 99.9% of the fuel rods in the core are expected to avoid boiling transition considering the power distribution within the core and all uncertainties. The Safety Limit MCPR is determined using the General Electric Thermal Analysis Basis described in references 1 and 3. .- Amen &ient No. 75,86

PBAPS Unit 2 1.1.A BASES (Cont'd) B. Core Thermal Power Limit (Reactor Pressure < 800 psia on Core Flow < 10% of Rated) The use of the GEXL correlation is not valid for the critical power calculations at pressures below 800 psia or core flows less than 10% of rated. Therefore, the fuel cladding integrity safety limit is established by other means. This is done by establishing a limiting condition of core thermal power operation with the following basis. Since the pressure drop in the bypass region is essentially all elevation head which is 4.56 psi the core pressure drop at low power and all flows will always be greater than 4.56 3 l psi. Analyses show that with a flow of 28 x 10 lbs/hr bundle flow, bundle pressure drop is nearly independent of I bundle power and has a value of 3.5 psi. Thus, the bundle l flow with a 4.56 psi driving head will be greater than 28 x 10 3 lbs/hr irrespective of total core flow and independent of l bundle power for the range of bandle powers of concern. Full scale ATLAS test data taken at pressures from 14.7 psia to 800 psia indicate that the fuel assembly critical power at this flow is approximately 3.35 MWt. With the design peaking factors this bundle power corresponds to a core thermal power of more than 50%. Therefore, a core thermal power limit of 25% for reactor pressures below 800 psia or core flow less than 10 % is conservative. C. Power Transient l Plant safety analyses have shown that the scrams caused by l exceeding any safety setting will assure that the Safety Limit of Specification 1.1. A or 1.1.B will not be exceeded. Scram times are checked periodically to assure the insertion times are adequate. The thermal power transient resulting when a scram is accomplished other than by the expected scram signal (e.g., scram from neutron flux following closure of the main turbine stop valves) does not necessarily cause fuel damage. i Amendment No. 23, 36, AB,86

'~ ~^ s PBAPS ~ Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.B Control Rods (Cont'd) 4.3.B Control Rods (Cont'd) 'i

4. Control rods shall not be with-4.

Prior to control rod with-drawn for startup or refueling drawal for startup or dur-unless at least two source ing refueling verify that range channels have,an observed at least two sources range count rate equal to or greater channels have an observed than three counts per second. count rate of at least three counts per second. 5. During operation with Ilmiting

5. When a limiting control rod control rod patterns as deter-pattern exists, an instru-mined by the designated quali-ment functional test of the fled personnel, either:

RBM shall be performed prior to withdrawal of the desig-nated rod (s). a. Both RMB channels shall be operable, or

b. Control rod withdrawal shall be blocked, or

c. The operating power level shall be limited so that the MCPR will remain above the fuel cladding integrity safety limit assuming a single error that results in complete with-drawal of a single operable control rod.

C. Scram Insertion Times C. Scram Insertion Times

1. The average scram insertion time,

1. After each refueling outage, based on the deenergization of and prior to synchronizing the scram pilot valve solenoids the main turbine generator as time zero, of all operable initially following restart control rods in the reactor of the plant, all operable power operation condition fully withdrawn insequence shall be no greater than:

rods shall be scram time l tested during startup from % Inserted from Avg. Scram Inser-the fully withdrawn posi-Fully Withdrawn tion Times (sec) tion with the nuclear system pressure above 800 psig. 5 0.375 20 0.90 50 2.0 90 3.5 - 103 - Amendment No. 73, Q, 86

PBAPS Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOLIHEMENTS ~! 3.3.C (cont'd) 4.3.C (Cont'd) After exceeding 30 percent power all previously untested operable control rods shall be tested as described above prior to exceeding 40 percent power.

2. The average of the scram inser-

2. Whenever such scram time meas-tion times for the three fastest urements are made (such as when control rods of all groups of a scram occurs and the scram l

four control rods in a two-by-insertion time recorders are two array shall be no greater operable) an evaluation shall than: be made to provide reasonable asstrance that proper control rod drive performance is being maintained. % Inserted From Avg. Scram Inser-Fully Withdrawn tion Times (Sec) 5 0.398 20 0.954 50 2.120 l 90 3.8

3. The maximum scram insertion time for 90% insertion of any operable control rod shall not exceed 7.00 Seconds.

f - 104 - /Wendment No. 86

PBAPS Unit 2 LIMITING CONDITIONS FOR OPER; TION SURVEILLANCE REQUIREMENTS 3.5.I Averace Planar LHGR 4.5.I Average Planar LHGR During power operation, the APLHGR The APLHGR for each type of fuel for each type of fuel as a function as a function of average planar of average planar exposure shall not exposure shall be checked daily exceed the limiting value shown in during reactor operation at >25% the applicable figures during two rated thermal power. recirculation loop operations. During single loop operation, the APLHGR for each fuel type shall not exceed the above values mult-iplied by the following reduction factors: 0.71 for 7x7 fuel; 0.83 for 8x8 fuel; 0.81 for LTA, 8X8R and P8X8R fuel. If at any time during operation it is determined by normal surveillance that the limiting value of APLHGR is being exceeded, action shall be initiated within one (1) hour to restore APLHCR to within prescribed limits. If the APLHCR is not re-turned to within prescribed limits within five (5) hours reactor power shall be decreased at a rate which would bring the reactor to the cold shutdown condition within 36 hours unless APLHGR is returned to within limits during this period. Sur-veillance and corresponding action shall continue until reactor opera-tion is within the prescribed limits. 3.5.J Local LHGR 4.5.J Local LHGR During power operation, the linear The LHGR as a function of core heat generation rate (LHGR) of any height shall be checked daily rod in any fuel assembly at any axial during reactor operation at location shall not exceed design LHGR. >25% rated thermal power. LHGR < LHCRd LHCR 7 Design LHGR 13.4 kW/ft for all 8x8 fuel -133a-Amendment No. /0, /S, 70, 72,86

PBAPS Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.5.J Local LHGR (Cont'd) If at any time during operation it is determined by normal surveillance that limiting value for LHGR is be-ing exceeded, action shall be initi-ated within one (1) hour to restore LHCR to within prescribed limits. If the LHGR is not returned to with-in prescribed limits within five (5) hours, reactor power shall be decreased at a rate 'which would bring the reactor to the cold shutdown condition within 36 hours unless LHGR is returned to within limits during this period. Sur-veillance and corresponding action shall continue until reactor oper-ation is within the precribed limits. 3.5.K, Minimum Critical Power 4.5.K Minimum Critical Power Ratio (MCPR) Ratio (MCPR)

1. During power operation the MCPR

1. MCPR shall be checked daily for the applicable incremental during reactor power operation cycle core average exposure and at >25% rated thermal power.

for each type of fuel shall be

2. Except as provided in Specifi-equal to or greater than the value cation 3.5.K.3, the verifica-given in Specification 3.5.K.2 or tion of the applicability of 3.5.K.3 times Kf, where Kf is as 3.5.K.2.a Operating Limit MCPR shown in Figure 3.5.1.E.

If at Values shall be performed every any time during operation it 120 operating days by scram time is determined by normal surveil-testing 19 or more control rods lance that the limiting on'a rotation basis and per-value for MCPR is being exceeded, forming the following: action shall be initiated within I one (1) hour to' restore MCPR to

a. The average scram time to within prescribed limits.

If the 20% insertion position U the MCPR is not returned shall be : l to within prescribed limits )" ave < 7'B .i within five (5) hours, reactor power shall be decreased at a

b. The average scram time to rate which would bring the the 20% insertion position reactor to the cold shutdown is determined as follows:

condition within 36 hours n unless MCPR is returned to 9" ave = 1 Ni[i within limits during this period. i=1 / Surveillance and corresponding n action shall continue until re-2[ Ni 1 actor operation is within the i=1 l prescribed limits. where: n = number of surveillance tests performed to date in the cycle - 133b - Amendment No. JS, f$,86

PBAPS Unit 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS .I 3.5.K. Minimum Critical Power 4.5.K. Minimum Critical Power RatiolMCPR)(Cont'd) Ratio-(f1CPR) (Qmt'd) 2. Except as speci fied in 3.5.K.3, Ni = number of active control the Operating Limit MCPR Values rods measured in the ith are as follows: surveillance test. a. If requirement 4.5.K.2.a is met: The Operating Limit MCPR values are as given in Table 3.5.K.2 71 = average scram time to the 20% insertion position of all rods measured in b. If requirement 4.5.K.2.a is not the ith surveillance test. I met: The Operating Limit MCPR

c. The adjusted analysis mean values as a function of 7" scram time ( 7" B ) is calculated are as given in Figures as follows:

3.5.K.1, 3.5.K.2, and 3.5.K.3. 1/2 Ni n O~~ 7 B =// +1.65 }[ Ni i=1 Where: Where: 7 = 7 ave - T s // = mean of the distribution for

0. 9 0 - 7"B average scram insertion time t the 20% position - 0.710 sec.

3. The Operating Limit MCPR values Ni = total number of active control shall be as given in Table 3.5.K.3 rods measured in specification if the surveillance Requirement 4.3.C.1 of Section 4.5.K.2 to scram time test control rods is not performed. o' = standard deviation of the distribution for average scram insertion time to the 20% position = 0.053. -133c-Amenchent No. 86

PBAPS Unit 2 Table 3.5.K.2 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES

• MCPR Operating Limit **

Fuel Type For Incremental Cycle Core Average Exposure BOC to 2000 MWD /t 2000 MWD /t before EOC Before EOC To EOC 8x8 R/LTA 1.23 1.27 P 8x8R 1.25 1.30 P8 DRB285 1.29 1.30 If requirement 4.5.K.2.a is met. These values shall be increased by 0.01 for single loop operation. - 133d - Amendment No. 86

4 o PBAPS Unit 2 1 Table 3.5.K.3 OPERATING LIMIT MCPR VALUES FOR VARIOUS CORE EXPOSURES

• MCPR Operating Limit **

Fual Type For Incremental Cycle Core Average Exposure BOC to 2000 MWD /t 2000 MWD /t before EOC Before EOC To EOC 8x8 R/LTA 1.34 1.39 P 8x8R 1.37 1.42 P8DRB285 1.37 1.42 If surveillance requirement 4.5.K.2 is not performed. These values shall be increased by 0.01 for single loop operation. t - 133e - Amendment No. 86- - - ~

PBAPS Unit 2 3.5 BASES (Cont'd.) H. Engineering Safeguards Compartments Cooling and Ventilation One unit cooler in each pump compartment is capable of providing adequate ventilation flow and cooling. Engineering analyses indicated that the temperature rise in safeguards compartnents without adequate ventilation flow or cooling is such that continued operation of the safeguards equipment or associated auxiliary equipment cannot be assured. Ventilation associated with the High Pressure Service Water Pumps is also associated with the Emergency Service Water pumps, and is specified in Speci fication 3.9. I. Average Planar LHCR This specification assures that the peak cladding temperature following the postulated design basis loss-of-coolant accident will not exceed the limit specified in the 10CFR Part 50, Appendix K. The peak cladding temperature (PCT) following a postulated loss-of-coolant accident is primarily a function of the average heat generation rate of all the rods of a fuel assembly at any axial location and is only dependent, secondarily on the rod to rod power distribution within an assembly. The peak clad temperature is calculated assuming a LHCR for the highest powered rod which is equal to or less than the design LHGR. This LHGR times 1.02 is used in the heat-up code along with the exposure dependent steady state gap conductance and rod-to-rod local peaking factors. The Technical Specification APLHGR is the LHCR of the highest powered rod divided by its local peaking factor. The limiting value for APLHCR is shown in the applicable figure for each fuel type. The calculational procedure used to establish the APLHCR is based on a loss-of-coolant accident analysis. The analysis was performed using General Electric (G.E.) calculational models which are consistent with the requirements of Appendix K to 10CFR Part 50. A complete discussion of each code employed in the analysis is presented in Reference 4. Input and model changes in the Peach Bottom loss-of-coolant analysis which are different from.the previous analyses performed with Reference 4 are described in detail in Reference 8. These changes to the analysis include: (1) consideration of the counter current flow limiting (CCFL) effect, (2) corrected code inputs, and (3) the' effect of dri111ng alternate flow paths in the bundle lower tie plate. - 140 - Amendment No. U, M, (0, H, 70, 86

PBAPS Unit 2 3.5.I BASES (Cont'd) J. Local LHCR This specification assures that the linear heat generation rate in any 8X8 fuel rod is less than the design linear heat generation. The maximum LHGR shall be checked daily during reactor operation at 125% power to determine if fuel burnup, or control rod movement has caused changes in power distribution. For LHGR to be at the design LHGR below 25% rated thermal power, the peak local LHGR must be a factor of approximately ten (10) greater than the average LHGR which is precluded by a considerable margin when employing any permissible control rod pattern. K. Minimum Critical Power Ratio (MCPR) Ooerating Limit MCPR The required operating Ilmit MCPR's at steady state operating conditions are derived from the established fuel cladding integrity Safety Limit MCPR and analyses of the abnormal operational transients presented in Supplemental Reload Licensing Analysis and Reference 7. For any abnormal operating transient analysis evaluation with the initial condition of the reactor being at the steady state operating limit it is required that the resulting MCPR does not decrease below the Safety Limit MCPR at any time during the transient assuming instrument trip setting given in Specification 2.1 To assure that the fuel cladding integrity Safety Limit is not i violated during any anticipated abnormal operational transient, I the most limiting transients have been analyzed to determine , which result in the largest reduction in critical power ratio (CPR). The transients evaluated are as described in reference 7. t - 140a - Amendment No. 33, 3%, EB, 78, /0,86

PBAPS i Unit 2 3.5.K. BASES (Cont'd) j The largest reduction in critical power ratio is then added to the fuel cladding integrity safety limit MCPR to establish the MCPR Operating Limit for each fuel type. i Two codes are used to analyze the rod withdrawal error transient. 4 The first code simulates the three dimensional BWR core nuclear and thermal-hydraulic characteristics. Using this code a limiting control rod pattern is determined; the following assumptions are included in this determination: (1) The core is operating at full power in the xenon-free condition. (2) The highest worth control rod is assumed to be fully inserted. l i (3) The analysis is performed for the most reactive point in the cycle. 2 (4) The control rods are assumed to be the worst possible pattern j without exceeding thermal limits. (5) A bundle in the vicinity of the highest worth control rod is assumed to be operating at the maximum allowable linear heat generation rate. (6) A bundle in the vicinity of the highest worth control rod is assumed to be operating at the minimum allowable critical i power ratio. The t' nee-dimensional BWR code then simulates the core response to the control rod withdrawal error. The second code calculates the Rod Block Monitor response to the rod withdrawal error. Thi s code simulates the Rod Block Monitor under selected failure l conditions (LPRM) for the core response (calculated by the 3-dimensional BWR simulation code) for the control rod withdrawal. The analysis of the rod withdrawal error for Peach Bottom Unit 2 considers the continuous withdrawal of the maximum worth control rod at its maximum drive speed from the reactor which is operating with the limiting control rod pattern as discussed above. j - 140b - i h Amendment No. U, M, 48, 70,86

PBAPS Unit 2 3.5.K. BASES (Cont'd) A brief summary of the analytical method used to determine the nuclear characteristics is given in Section 3 of Reference 7. Analysis of the abnormal operational transients is presented in Section 5.2 of Reference 7. Input data and operating conditions used in this analysis are shown in Table 5-8 of Reference 7 and in the Supplemental Reload Licensing Analysis. L. Averace Planar LHCR (APLHGR), Local LHGR and Minimum Critical Power Ratio (MCPR) In the event that the calculated value of APLHGR, LHGR or MCPR exceeds its limiting value, a determination is made to ascertain the cause and initiate corrective action to restore the value to within prescribed limits. The status of all indicated limiting fuel bundles is reviewed as well as input date associated with the limiting values such as power distribution, instrumentation data (Traversing In-Core Probe TIP, Local Power Range Monitor - LPRM, and reactor heat balance instrumentation), control rod configuration, etc., in order to determine whether the calculated l values are valid. In the event that the review indicates that the calculated value exceeding limits is valid, corrective action is immediately undertaken to restore the value to within prescribed limits. Following corrective action, which may involve alternations to the control rod configuration and consequently changes to the core power distribution, revised instrumentation data, including changes to the relative neutron flux distribution,for up to 43 incore locations is obtained and the power distribution, APLHCR, LHCR and MCPR calculated. Corrective action is initiated within one hour of an indicated value exceeding limits and verification that the indicated value is within prescribed limits is obtained within five hours of the initial indication. In the event that the calculated value of APLHGR, LHGR or MCPR exceeding its limiting value is not valid, i.e., due to an erroneous instrumentation indication, etc., corrective action is initiated within one hour of an indicated value exceeding limits. Verification that the indicated value is within prescribed limits is obtained within five hours of the initial indication. Such an invalid indication would not be a violation of the limiting condition for operation and therefore would not constitute a reportable occurrence, e l l l - 140c l Amendment No. 27, 36, dB, 88, 70,86 7

Y PBAPS Unit 2 3.5.L BASES (Cont'd) Operating experience has demonstrated that a calculated value of APLHCR, LHGR or MCPR exceeding its limiting value predominately occurs due to this latter cause. This experience coupled with the extremely unlikely occurrence of concurrent operation exceeding APLHGR, LHGR or MCPR and a Loss of Coolant Accident or applicable Abnormal Operational Transients demonstrates that the times required to initiate corrective action (1 hour) and restore the calculated value of APLHGR, LHGR or MCPR to within prescribed limits (5 hours) are adequate. 3.5.M. References 1. " Fuel Densification Effects on General Electric Boiling Water Reactor Fuel", Supplements 6,7, and 8 NEDM-10735, August 1973. 2. Supplement 1 to Technical Report on Densifications of General Electric Reactor Fuels, December 14, 1974 (Regulatory Staff). 3. Communication: V. A. Moore to I. S. Mitchell, " Modified GE Model for Fuel Densification", Docket 50-321, March 27, 1974. 4. General Electric Company Analytical Model for Loss-of-Coolant Analysis in Accordance with 10 CFR 50, Appendix K, NEDE 20566 (Draft), August 1974. 5. General Electric Refill Reflood Calculation (Supplement to SAFE Code Description) transmitted to the USAEC by latter, G. L. Cyorey to Victor Stello, Jr., dated December 20, 1974. 6. DELETED 7. General Electric Boiling Water Reactor Generic Reload Fuel Application. N EDO-2 4 011-P- A. 8. Loss-of-Coolant Accident Analysis for Peach Bottom Atomic Power Station Unit 2, NEDO-24081, December 1977, and for Unit 3, NEDO-24082, December, 1977. - 140d - Amendment No. 36, dB, /0,18, 70,86

I 2 PEACH BOTTOM UNIT FIGURE 3 5 K 1 MCPR OPERATING LIMIT vs 7 1 FUEL TYPE ex8a/ m i l l i l - =.. .. 1: .. i n. ci....1. .. t. _.__ :. _ i .I

.1

. _l_:_ u.t.._.. 4.. .)..... I I.. 6 4 .4.. , ;j. . g.. := ;--. g.: :... - 23:,4_g,... j;- ; .==:jj:. 2-iid:j;f.j-. f. _.i :=g.:-if j.J :;g=jij ij. - -g;q g.glj;_;n u 1 2 'JJ ..,... l} :.

2:!

1.40 i l.40 ....... _ ig.. ; :4,,._._._ 4___ . ]. g. g g... y]..g, . g. _,._. 7 ..l. ..l._._,. 1 ..I .. 1...... _L .;4 l -l...3".;j..jf;.l .j_ jj =- j. - '), :i:.sjj:[ i )

ll_n__.:u G= 1..__.. d...... _... d.i

- l. m i l .] k/ .}- .j- - .l f j._

l 1.35 1.35

. :-'_:}

. : u.._-- +{.... 'l." *I .[ ~ i-- T.- -

• f...

l ..j. ~ ~. 4.. : q. + j 3 C._...:}..... . ! Z ::k..... ;-*.. C ~. ,:3_*---..M..;*.-. **... }:: :. ".-. y '.!F i.. b-) b 5 i! ; -[!l 5 1.30 1.30 . !.M".... ....I...... I _.....~... C._--l 4...

• * '. :. 3 :.......

{._. ,n .1 1 ..p "3 !p '.iZ- :d.ii--i]..i:- i.. l - 'f- ?O h t f1 -i:24; i=41=i==4 -i=!! :i&SX=i=. it.

j-=.

E a tii -:c= 1+ ; i @ Z W -i==1 W.iji=: _ij. :ij.;;;;;4 qi=I :=!" di::g4-K:ii. -} - }.;.. "ij 1.25 l.25

.1.x:.. :-: :_--.

.... 3:.: :: -i !_: 1 1

i :

.j ::!!;$::-j=iji.,i -[.ij:i-jul-j:- :iiiil:. :ji : .-l_ :qa .l 4 ] jj.-..nj. q. .jj.. g= .;;= j; l

- - J j.. ;j --i -

ij: iii:--{: "!:

j- "E."ij: :

j ..l .l l .q .j 1.20 l.20 O .I .2 .3 .4 .5 .6 .7 .8 .9 1.0 l OPT A 1 OPT B 7 va - Amendment No. 75, fp, 7), 86

\\ PEACH BOTTOM UNIT 9 FIGUREL1:L.2 MCPR OPERATING LIMIT vs T FUEL TYPE P8x8R . l =2.1= = k--fi=*t-LP it'==t.. =t = : 1.i -i

~~ : ~.$. ~ i: ~.-{!T.T..j.L% Z.

. C.*C 1. :. ' :- . '.~1.**.

3.

!j..:.': .......'M. :- ".= j '.", .... J. i 1 T. ....] .y... ...,...T~,. .ilj.* * ;-' (5. 2f.:i{Adi,-.j.255";ll .l.... l.40 .P ' : _... =E.... j __..3....1 =. :... L...:/. j =... -.j : =_._=... : I.40

2....

...8 3.... n....1 _... :1...=_ _.....:r. :.. }. .--l. n ":

ii.=il

.r'd?$- itii. -.jP/' ~5 :lli~ ?= ..zi: 41.. ::1.i "=:!hiEi=ji:3,- p Z.3 1. f Z j: .:!)1 2. _h ~ : ] _ EMM$ in ~ l._: i1

i/

i T ili : 'l~ ^ - l/ M7 M i-li iii=.... f..,.__ l. _.c _.. g:/j. i 1.35 1.35 .g j .I-3.'il-i57 b ~ '.~-Ni; .N.' .f E - ::% 1 il 5 f -j =;=fi=.lTliE d=[2n: ;!iiE].ir..= j,fK::: -1 : .... _1.....=._.=.-!. .. u. -... ..E....._d.... f. l =. _=r. 1 _.... l...... 4 =.......i.u.. =. .. =1_ :n.. ~.. =. =.:.: n.... /ilMi i;. ilE M5;; =-d:~E!5i36 !;iiNT/[T'.+. hi:F"=l"+"' l.30 l.30 .4. _. ,......._4_. =...._..... .=....@ .-] =. -. ...l_..=.. -4. =_...... : =... .m.. n..

2-Q[=. -ti!Ei~.-~}:

;

. ij::...;;. --ii;i :.==2it.]f. -l.i-T Pii="a.biinli53:Wi=Sl===IlE 2 l - il: $2: ^ E l- :.e !FA=in;+ iMiiE':H =* : #.~ =. ....:1.,;ji!;j;i-iqEj--gf= = := - iii: :];;;;;=: :49 =- l.25 1.25 .:lx.. .l yl.. =.m.3. _. =3 = l.... _.- .=,=

=e

---

f.._.._..__ =.

• a:

x.. "$j.:253: ..Eih 35555.55 5.5 - : i*.j~ii.if35.5 fjf t:' f.:2..hn;;q. 3 . !! -! 5. ** .f.'_...i:*;:- ' " * -. j h. 5-d. '-- ' i *itlI ~*

5. :'

• f f ' ' **i f *- !
• f

[. :.N k *l {.-*2: ~~i! { i !!!". " "

• LO..~

..i .1......... l.20 1: 'i. Z. ;-~~ : ~' I.20 l. .g. 0 .I .2 .3 .4 .5 .6 .7 .8 .9 1.0 OPT B OPT A T -1h2a - Amendment No. 7%, #, 79, 86 l l

f PEACH BOTTOM UNIT 2_ FIGURE,.u.3MCPR OPERATING LIMIT vs T FUEL TYPE P8DRB285 =l::--rsli =i- -il--Jin.=h :li:.i1....:241=i: :1:.i.=:t-Eix- . !: -;l r. - - T:::F=;j.-tijiE_t.;j=igEj]....... . =. = = :.= = =....... . w =..=.=. _a...4....,4._.: c.=. l.;..=.tus.4 2:.===.1Em:im.. ..;;j.23.. f =:~ l40 .i.:u----i.i..i'._.=Ltu. ._r.i.r.ic E_=_.i.=H=_:. :. -=. rf-E.. =. +1. _i::. I 40 .-. -l :"i= i; 19T.a :.I ii:=2._ :IrlM[ l~ ".:li: C~ iic+}:: u,;gEmag egsPgE.):=iE-ij.. =]Ec r -l;. a. . gh -l - )-. T 0

• i.%.

~ '. ' ...'3

r : r..y

1..:= :

u.

l.35 . Ap==2-q.. - i. :;,--- :q

j -

i.35 .t = .z;= -. =. 1

}~~NI-id7E;hb !I5E b 5555- } 5.5!5l:~iEi.1-l:[i:ll ~I!'-

il: =~Ki.I ".:ili_ij-~i. ijj..i-iE ; iiini:j-- g[.-iLUjii.. - uau =2-

.2: =.

I. ' u.:.... 1 _=.._t==

=

.{.i=-.;. :.pf.:.np..... : ._ 4 m... . =. _ n...._._._..._.. [ilEi:.3 -j':i' il=..___.. _._.Mj--(ij;Eg.~s :j.{ "i=[jj". 4-- 1.30 2 1*30 BbcWo:hcuo'srD/52.):i=i $iEi'"figg]" Mil ji3i3cj; i 1-@: 3 iEU4iipEi!41{i"i lit !!! H ii~ "Eil':: .g_= c.;;i=in:"U j-l==;=;,j=j :=3. " Ein l:..: :..Ej:. :. - - = =- = :P : :-- u. uim i..= : __-1. = ::. _== : - ..: === t - ...=:. - xu a.==. = ..1 c. t nl-

=-

fiI}3:5}ril;!EiiEEiIi!!!iii'.:i!N2'"-l=.125-}UI~'5}'I 1.25 1.25

liiiii...liCli.. ::

...... 9 n : :- i 'lii:il!=:i: -- - -li 9-i.d......E .ill ;~ ijjp "i:ugljj:-iiif f ;.llu :,..

j.

!-{.i= jim i-iiic

-l 1:

h ;

p

ii::

ij; i;i-injr:in" -: e

!'.p.: ut

'i - ll! :!!: q: ="i:nji= j "![- :: g'. g g

r-l.20 1

l.20 0 .I .2 .3 .4 .5 .6 .7 .8 .9 1.0 OPT A OPT B T 42b - Anendment No. 16, #9, 79. 79, 86

1 / y3Aps UNIT 2 ~ a "*; ! i i!:i !si: :: ;h; ;l[! ,;F,.;! :,. ., 'j'i yl,ii[.! i'i[" 8.i jej;h"!. i!i! 'li: [jj T* Ul I!f. i[!! i3!, I;', T* im id! i-

?ti is;

". 4it [ 1l[: lt i ;- ,.:t i , :t :?: - ! '! ';lj II!I }Il ! I' OINlI'di lf!}li!II Il-Ii i I!i i I 'l ' Ii;i [ij IIi , g.: i li li ! li '!! l1 ! l'l! ,i i i

i i!!.j

'i..l

)).,.I : 1.1p T.,4.l-.l 1

.ijj g 4 O ,l L l .T "' l ~ I' .gq h l" l ] l [ l l )' j I ll 9!: 1 1. i i d ' !l l l ...1..l d .!i I l g5 g!:st .,. f 'f 'l ' D t 'i Il!ITU II F 'li D I "I iij jg I i i i u, x.p t.n.. . c

i. i nI wp,.,,w, mir[.in...)

79 ,l. O A 4 1. 4 4 N i.. 4. 3 )l51.. II I! d { !!i[i ..Si ...o. !..g e E-* f Q ~ {.g iC d! !Ii i HMl*,}!!. ii ![iQ 1 ' l l 8l! d iN i ll !i!i i g .l 5 J !!!! ! I ,il !O I: i 2 g l l i i f% iii H g : $ >.d M5II h E* !!iW @[II .i k I.'. :. j!i l'i ljj lli ii' jji! !!!! ll ! l! I i ! li! c' ii i I '!;. !.tI Ill' II 11 I!I ' !! ilNI'j II}Ill li i 'i Illi I Il dIl I'I i II il [N'fi! e I !i ' !!! li! ilI '!! ilj/ l' Ti li il l 'j!, !Iii[ iiii iii! 9, jfll 'ITi 'TiTiji j! il! !l lli l -l ' 'l !in ll! i"'![ i liiiiiiii ;il i i lt lil i J N , jll

• 1[I"IIill IIII Ii l 'III 'jfj l ll ii i !! ' lil! l! i; i3 hl i.

F d l'B !!1 1!ll !Il t $[ I II I 'l ll! l[ ! I I I l ll ll l t m l !l I l ll lill Illi il lIl l i Il I j ll! Il fl}H l l!f il @I I{s s ti' l 11 1 l! li il 11 ii ini!i,jii !iq !i i'i l I i g ji i !!l '~ Inl i III {[I 'j I! lji li il !!j I ii " j, ' i 1 'i l'i il i 1 lT F l lIl l$ hl!II ' Ij;;ifl l [i i S 'lll li. ' ll i ['l till - till i 1 'i i ll11 i 11 ilil il 11 f I.D l ll Ill i '!il :l l ill, "'!I'$ f I' Ill"Ii3 S" I,! g. 1 f !n il il I. Ifi El' !!!l I ll ! i il!! !: l I ji ll. .,1! !!! i ' lh c. {[II'i! li 11~I il ll!f'.di i!!! 1. Iil I.I lii! ll ! I!!! i !!I II!j "Ii"II * }lilbi'II II I I! IfIlil T 'liI '[l' f' 1ll Il i !! i' I li } , i I

!!! ifl 'ht i llil

'l ll!! iih lIIIIi! Ill i ll!I ! IlNI'I i 'II o o o o c h h h MAXIMUM AVERAGE PLANAR TmW FRM' NION RATE (IV/JT) "' O Amendment No. 86

,~ ~ PBAPS UNIT 2 ' i !!!; :4:.' G ! N .: tii: 1:

• ! ij'i ITii flD !!Ii [: b

• I!i !if :[ '!*I i

Idi i 'fl 7. I "J' 5 '. "ii! JjPi{ 10!!i 'i h :$ A l di i Okti lI0f iii li!:!!il W ii! iU'! t !Ji ih n!!iliki !,tT i @ it.is-la ll'i lj U i .lj fil i.Wi ill i l !h 'i ' i 18i II i )j; .l Ill lj i i l j.p ' j,g".. 7 l-o i 7 j q 4 y [ I! n! J': 2 I l l h;../l [llg 'l r: l [. J. i h ['l 'h:l!. 3 S. 7 -U J r 4 r JT i ' h. hi i k I b,I, 8 E ". 8 2 o gg r - ~ i, i IkIh j[F i l[' f9' i '.H.lid,{'p[ I' l [' l U il+! I G l l lI! f'" h[: 1 j i a ' 'I[ si.. j g;llQ,, 4.. 4 g .g .) 8 ik !!! h! l l I, l fii ~ lf)!M h" I I "i M j g 5b $d M l!i!I'IlI $ "i MIfl 0,I;!! Ilj -!G' fi gi 5,$ liN fj III II I'lIlSI ili !!j ii! 1i "E "!<([h.f d Ea It1H ?!: :ld[!t ii t-li! n 9 al!N ii: :1r rti u i f,t a i 1 : up! jn . !i p "3; l e.3 i:* ii.iiiT r'Tej ll k j o m h !! ![ l}i !

i, il b iIl I I'If11I$ li I

ii i ! {i!i illl ! ~ _I I

.,@il p'

E O y i.. !l 3! fjj hji li j I IlI h ,;. !j MI lllll[ I fl . lIlliIk lil l!'I I l.l II )L i i p !!'- ifi !5 l m 34 li IlI .; I.I..[$ };.!lill lh IIII I T I I [, lii;: ilII b{[l . f.fl h' :' i d I ! Ii I. ll ll!i Ill ! ii i l i l: g m d i i l I I ill ~ Ii 11 ji' L /l 'l!l 11 ii l i !Il P l l! !j![ l pi ' l "I1 5 il [ o l l liIIi li.bII Ill! li 'll! !l l il i.Il I I III' i! lI' h. } j !!ll Ilil ll l "Ik'I' I_ T "l- ! I i [ ! ll!l 'll 'Ii I i il ..I h I l 1 'l [il } lii! li I". i j g N' I 'i' 'g- " "I n lil! itil l}il .' I il li . }l Illi '$$ #l d i l liit],'ilj j{', J' "i ! l l '.i l! l ilIIIII llll li l!!! II lli ilI III Di liTii! I o o o o p h b 5 MAXIMUM AVERAGE PLANAR IR EAR EEAT MION RATE (EV/IT) Amendment No. 79, 86 -1d8-

PBAPS UNIT 2 'I! *i ih i!! llh

k...

II; g pf i;II iih!h.!!!: th 5 r

n i

y 27 . 4;4,

gn;#

l ..e

q

[l! 9 [Il i lj p N! !!!li!l:

ll r

,j ll i ;

!?

'i : i l ll] i h !l! ii l, II illl III Ii. $! lI h i. ii l!! 1 I i l !U.! ill f l? ! ! i. !( !!! d 11ll I ll il l l [ o i n 'i I. Lli] g 5. ..i [. g O, c3 dll li l . l, . I

c.

[l." '[ } h i i .i i ,i } ~j ' "i I ![ T l' "itT 'l i ;ill { A j 7. ..b. N kN I i i m' k I I h h 7'E N' T 'Illi I !41 li ' l i '( i 19 o h; m i l m !m h: W '"[ "l 1 t 5 i Fll (1 i; JJ ;, l i.t 7 v li,j h ]o' J. il~ di ii t J i .e j, ij fghl,lf ) @ kk h 5 h1 [Mi !?l !I Ilil !I IIlI d ME 'iff [l y(i[j!ijij !! ! I!!!j'"j'rl l Ii i li !' iI t h[ii ml l @ $2g fllI.$i 5l l[h gj r ,3 T y I i !!!i iill i m e m,- ir' pj i! T l li r'd 1 j

.j.. j!

- r i

i:

t... ;gj li !)) pl'j j!'!1.j

!!,j%,i! o y;. jg3 = ".h - !!E ! l i a es . Ii

i. I :j

- j[ i[ l u r I i! .i i i d E 'I.' j!l' fi ill ili iilI i !lit il ! ! ! li! o' 6lIII l~l I$ ili II fil ji!II II [li ',Ii! i lii' i 'i i. Il iil i g lF. !.ii II~ [l 'il l[l! W i l! !g g t ll' li ilI !1 lli !!!i i 'l F lih g ,2 !d '!!! li! 'j ll gi IP 'II'glh':}lI [l dig;ld id 'til !!li .! Il fif o i Y I!! liiI ll I la Il! m M i M 'i!! i"I 'l y !!] l l l 'l !I 'l I il ! !! ' li!! !!ij 1'1rg ,1 l !!! 6 5 i ll IIIb [t fi l Iif I I'il III !l.l tii! M:

ii iii!

i 11_! g M Ii l19 h I OI !!l !!! Il!I ll !i llii P i i[ ll I$ j NIIiil! ii" I fPJ lil! Ili 11!!! ! Ii! IIEIII liii.Il !iii}fii l!P T1 E i li o Ibi' i[l'-fi ~".Il i e' !iii if ! 2 } l j f' !! Ig 'P lli Il I'i ilii !!ilili ,'Il IE ifi Ii!' I!(ll!l Iiil Ili ilI "i i 6 l l~

{ i i lII.ii ilil 11l llll ll t fl) fi' I

fll i j (! [ ! iD! ll lli 1 E llII IIIIIII I III$. If IIII'i I i !i II II!I II IlI'l.I i s'!!! j,1l, ilil i! Il ! llh !!! 'i lll ll l lll! !!!! 'lli l!!!.jil ll!: lijl l 6 I[I!I illi llli !! - t l ! !!;! 'h iH lj. hii ll l jii! lill.!jj lik lll llll lp i m

ill liil ili!

i l.il l 1rririiIiii"iliti tin' liti l. illi 'hi 'illilr'!! j' I liii i I W' ll illi I! i iiim J.r.' il T'h. D. C. C. C. ..? E s l MAXIMUM AVERAGE PLAMAR LTWRAR HEAT GENERATION RATE (KW/IT) Amendment No. 70, 86 -1h2h-

W H; i.!:.i

i-

.- : ': :!i! i!6 liii 3!' liii :!if ii" ui iil: b:!I $i O!!j'il ibilI: b .c .it: i..

I!.:i! iii: !!!; ?di iki ili i!F 'ii; llii il. ii.:

h fIf [f h I f kh f g iii O ll!! !!I i!!!!.I illi .il !ij llI i il! ! - li 'lli Pfij!!!'i! ll l !!ji [;j: if S hi P!! ll l ilIl'i i li!! 1 ll h!ll fil i i' ii !!! [li li!! !!!! ',i lii! llll j i !l}liIIIgh; h 8 !L i' i 8 il[!ll' l! li ll l l ii #M i . Il Li L!! !l.! fi li9/f!! y[i Mi ll '.i!l !!! Fl! ! Il !!

1 iii dt;.lii liij i Il!

lii '. 'g o' ql il '!il illi lIlijllq!, .iti liii l'il llil lill lll !I I i lli ! i ik[ !!! 10! !!! !i!!-!il! ll! ll i tti I fil' l Fi li!! !l! I i g= iFi Llill dil L ll-I. .ii il - l ti M i i l i 1 i b 'l 'il iiy gf

0 ih i li y

!!!i !!!! i.1 fill l l! Il I- -l'#T lh ! fi.! i 1 2 e i dg Li - 'i ! 5 l tin!i! Hii L Il !!! 1 1 i i t l I 6 H' L li ' [] I [F liiTil h N ? li!! !!! -lill il ill i I i! / 'ii II I l [ ^ m g li. i.: Id! I!!i i l- ' ll F.I il , [{l i SI; !! [11lI F Tl 'i! Oh l4 i j' ',j l!h lll i '1 IHji' 1 y'; g l ! ll 1 11l l'!l il ll ll 1 l !l i gg i iHi j!i idi il!I i ll !., I !! in ' li! hi i il i! I'i i!!! i!] ! i; 11! o ic e lii Illi l iI ll 'i ill: {$ y$ [iiE Iiliilli liit i l I[!Ui! I il!I ! ll i i S $kfM liiN !d d h hh.kf h Y g l 3l b l.2 5 jd! ! !! y! .! '4! !il.i!!i llll lj. Pi li:

11 !: M E!$

ij.. 'il if lili i!!j (!! li; -[Iil! IIII Ti7li!IlI !;if !Fi! INII k Ilii Uli fili ii!NIk l l .:r e h hf!ilf$h,hhl$ $hb N !h$ @ i 5 e!il! stm n'!I!!guiml!pqu ell, p!,im z e,- i ll illi ll': l i :lli i iii' t,: ill Pi l

I

!.l li ti.- I 'i!' 9 $ft[: !lli.II.!!! M.jl!! II !!! !!! dj ji'3 !! lE![j.% [i ltli i! i i!! it! !!!! O!!lii ii l 0: h i " tr: IIT i! !! !!!! iI lii i E ilHliMYllM $ @MMM l ! b. Ili; ~ !!I' !!!I U[.l!..idh !!.i!Il[! [OOh!h! IIt! !!il I Ikidil!i lil! Iii lli- ! l i ii iii! llii #i! !!!! !!!! liit !!H Ii!!.0! }$ h II 8 !li !in itii @!m i$!p.IC-

!!t !!!! !EEME ll!!!!! t! l!i $ !!i

E bit I!!i

!i fi 4 ,ii! mi !ili 4!!i illi Sii tii ' I!iil il! lI!! !!!: T Ilii ';:i

!ii ili lill lill !il itiiti 11 2 !I l' il llll i i !![ 1"i !!!! iii! th I!!

1 4 ilii, til lil! ll i l'ii,!Ill !IY 10 idl !!ii i ; ill, ilii; !}EUI i! ii l,! g ll j ll: h ii:1 llii i!!I liti i![!IiliIIlt!lif ii ild lj!! 'til l' i !!,i uit i!!! Oi! i!i iii iH.lii liiN!!i !b;! 3I8lili lti! !il !!i !!!! !!n W i!!h @ '^ If ii! h:@l@T}!ij til '!i "igij' !O! @ idij 'Utl ll .i !i ill: tili :lil Hit!Mi, !,i j i!! :ii; !!ll !!!! i !!!iih

!; iT ll

';i' iiii iliiIFi ti!! !!it sii o

o o o o& A,- A o MAXIMUM AVERAGE PIJLER TN EEAT GEERATION RATE (DI/IT) Anendment No. 86 -1h21-

j I a f! ii:i :iii (: Ei! TNi iii: L:-

i. ";

! :

iii :. Il ; j;!; ;!E d lit M i*"iTTi*! ::u "I:i p;p i::. !T. i:l: ip..:. r- ::. I u.; :n! =i .:n

...n

i-1-

in

. int :p

s!

i:r t mi m; !!h; j! !! hi!.Nf,Ib l l l .!j.II! !N Yk ll hl!ll I l:. sii ! !: $ lil: lii.I ! hU 'i !i! Oi id! i ! Ji.Ih l!!' i' il i;.!!! i g!!!jjj{!:1 [d j g bi li!! !! l !! I '(i illl i' I i til i ill ii ! i ;l il ni N! I4!j Il l il i I 10 !,! l l

ll ll l i

Fi li ! li li.I li Wi !lf O ii!

l1 li.! i.

I 1 lll 11Hi l l ii .O !i ! ltil $1 ii I il liii 14;

ili lii lii i

} il !! lil . h !! ! ri l il lll! li!i liD lii I?i lili ih E l

ii liii iill-

'il l l - l! - il I Hj' l' ill ! i l'i! !. y ;[t1jj!!Kl{1i,ig g S,

!!l ltii Ilii

. !! ill.. I!! ill ill i tli ii I !!.! nl. Ii!! !!!! I iW!i 4 1g ll!i riitiHHij l!U ik li i !L lll k liU ll il I il !! ! @ l# l iib Eg itii !!H illi fi:! I t ! l i l.ill ill $ - tilti li !! i &l in! illi gg nii !!N - ll! l !- I l i ! I I I l l:S - II (j .. llj [ 2 II! ljh 6 R ;'s f 7: 9!! Hi I i i M i i U l! I i ll l li ! lil..liAl i 'i l i!!!

Et! i

0 n !

'!!H i iI il i i i ',! H! @ Al$L.1 ,W!!b g

idi? n't I;i i Illi I; i.!i!.il l

li i ! lit li!l w lil li !i i [. l 'l I " li! 'iii ii i"? P Il jj!; 8 ll l j; I! lli.l m ( H j;r-,lir-g. li 90rif , 'i N 'i I i iM -r -l,t.'l i n i l.T g T:

!P i l ilil g

Ii w o i" VM i 'li i i hl2 llP hjj i! ll!; FI ib b !b OI!bl b h "! !.!N.!!!.'.Iid gil.ii h h l['l .n f A g*

4 :"i h:

!!! l! i g di lhi D! 'i? 'd i. ! !! ljj] IlE l!!! ijI o c: i..--14gjj Vl! !!D Iii ill: in! I ~4 ' f"'

l /;

0. >;! 6F r-64 lii li!! !'c ',; i N~ili,' ~ N M El* '!..U .il? 2 m e b 1 in ll11lli! l !! IT. !!j!,l 4 o

i mi

i g

I' e ni. l

c e

F'

. tilj !!i 1 ii piin I

]p: ".i jili.U!!!H' lli! e oi .: ' 'l" i,! i j' iil l:l ji pi[_g fM i n 24:. I 2u a tN l o; U i p l c a ,! Hi! g:.i! .e IIll l ii : Ili.@ ili !! ! tia .g f,n . llI i i

!. i

!!i I: iM.gp !!!!iijit Tj lj!i !!; ik. g g i!!! lJp! !!ii Fie 181pl l i g ,x j!5 ili fi; lli; n! .!!I ! l' !!:- N

." tii!.it J!I III

i 7.illi l His L

in: ilii !iii lib '. ;! i!! nii [;l. !il

'!F.!!M!hsiiiS!!L'!i a!!;' hu.!! kjih h!11P1P.g!!IF!!qWl!L L!!H a e lii ltil !!n il:l 11!' Iil I iii e4 I'Ip lat i.'.lg iij.d;: ..:: e .il pl lW la . :l ivi i -l .p- 'ii Pu

;i a

d .i.

;p! p[

i i.e. lgl;I! - i I m qji ip .a. 4,. o I lih ll i il il; I! i i I ; kn iin Hq!. till ll! ,!i !. I Inl iH: !n e e .t-liio--lil' dli Ik -ji! l l $.. !ijj!. j;ii illi iih !jil !!;' H i lii. E hk ll!! Mi j!li..ll r"Vjji [j t !!!; I! i f.I ! if' de! tr .in I.. gj

-H b i

i: . :t m .n :T...: n - --hi in un.n, i.O.!- ii D ii;! !!; ju,!.!

n_

iii i.

w 4. ,jl! iV lh Q4ij!!Illg.- @il ,3.]3p"li .j'.i liti. li!; ljjj plf-1 I it [rg'vl1:

p..

.r ok ,d_ i j i p., p e tr J: L )lii i o :;!. 10 I:!: lhi lill I il i, n m il i li.,; .10

lii liu.Illl ill Wl lhi Q b !ij jhi jj i l'{j,in"i!!!! ih! [1..!il I! I la I 4 ji p II'lj iiii !! ; ib Ili; !!h ! ii !i ibi i!ii lill ill ilii !ill !ii C

]- t !ilj ']l!' H:ll lij b:t i!4 Hi! i!I iniI!i! lii !!) 'e!!l Uli bi !.ji !H! jiji ii;i b!: }![l "i :ll; i, i p p. :p; im i n.. -:rvE m: iti plj g;r t :i :it: in 'in, _]: m mi ,i l. i. r i i m

i n* gg

, g p-g u.. l jij.iiii Uli,!!l fIl Oil 00jdj Y!!kis, '!j[1[!j f'.itlhl. I f'!i j"!l1.' ;llI iti{!!l!!]' ib lii! [IIIlli i illi tili !!h iii: ! it iiii$ i:P ;;i- !i-di; Uh \\ O O. C C 9 m m e o m t e e e e l MAXIMUM AVERAGE PLANAR LTNEAR EEAT GENERATION DA'T'E (KV/3T) Amendment No. 86 -1h2d-}}