Text

Unit 2 Operating Procedure 2102-1.3,Revision 14:unit Startup
	ML19224B180
Person / Time
Site:	Crane
Issue date:	03/20/1979
From:	; Metropolitan Edison Co
To:	Mullinix W; NRC/IE
References
	2102-1.3, TM-0014, TM-14, NUDOCS 7906140170
	Download: ML19224B180 (61)
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03/20/79 THREE MILE ISLAND NUCLEAR STATION UNIT #2 OPERATING PROCEDURE 2102-1.3 UNIT START-UP Table of Effective Pages Pace Date Revision Pace Date Revision Pace Date R evision 1.0 Ow c2/77 4

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Date Ocgnizant Dept. Head Ccgnizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Recornmends Approval

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Unit 1 Superintendent Approval Unit 2 S erinten t Approval WY kl Date

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Manager Generation Quality Assurance Approval A

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06/22/77 APR 2 'J 1313 THREE MILE ISLANU NUCLEAR STATION UNIT #2 OPERATING PROCEDURE 2102-1.3 UNIT START-UP Table of Contents 1ECTION PAGE 1.0 REFERNECES 2.0 1.1 Drawings Applicable for Operations 2.0 1.2 Operating Procedures Applicable for Operation 2.0 1.3 Manufacturers' Instruction Manuals 3.0 1.4 Applicable System Descriptions 3.0 1.5 Curves, Tables, etc.

4.0 2.0 LIMITS AND PRECAUTIONS 6.0 2.1 Equipment 5.0 2.2 Administrative 9.0 3.0 PREREOUISITES 12.0 4.0 PROCEDURE 15.0 4.1 Normal Unit Startup 16.0 1.0 190 215

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UNIT #2 OPERATING PROCEDURE 2102-1.3 UNIT START-UP

1.0 REFERENCES

1.1 Drawings Applicable for Operations.

Main and Reheat Steam, B&R Dwg. #2002.

Bleed Steam, B&R Dwg. #2003.

Auxiliary Steam, B&R Dwg. #2004.

Feedwater and Condensate, B&R Dwg. #2005.

Makeup Water Treatment and Condensate Polishing, B&R Dwg. #2006.

Feedwater Heater Drains, B&R Dwg. #2009.

Secondary Services Closed Cooling Water, B&R Dwg. #20l?.

Circulating Water & River Water Chemical Treatment, B&R Dwg. #2021.

Circulating & Secondary Services Water, B&R Dwg. #2023.

Reactor Coolant Makeup & Purification, B&R Dwg. #2024.

Intermediate Closed Cooling Water, B&R Dwg. #2029.

Nuclear Services Closed Cooling Water, B&R Dwg. #2030.

Sampling Nuclear System, B&R Dwg. !2031.

Nuclear Services River Water, B&R Dwg. #2033.

Reactor Building Ventilation & Purge, B&R Dwg. #2041.

Reactor Building Normal Cooling, B&R Dag. #2046.

Reactor Building Penetrations Forced Air Cooling, B&R Dwg. #2497.

Reactor Coolant Pump Seal Recirculatin & Cooling Water, B&R Dwg. #2501.

1.2 Operating Procedure Applicable for Operation.

j 1.2.1 2102-1.2, Approach to Criticality.

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l.2.2 2103-1.9, Reactivity Balance Calculations.

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1 Revision 0 05/25/77 1.2.3 2103-1.10, Heat Balance Calculations.

AFR 2 3 1979 l.2.4 2104-1.2, Makeup and Purification System.

1.2.5 2105-1.4, Integrated Contr;l System.

1.2.6 2105-1.1, Nuclear Instrumentation.

1.2.7 2106-3.1, Turbine Generator.

1.2.8 2106-3.3, Hydrogen Seal Oil System.

1.2.9 2106-1.1, Main Steam.

1.2.10 2106-2.4, Feed System.

1.2.11 2106-1.2, Extraction Steam, Stage Heater Vents and Drains.

1.2.12 2104-3.6, Circulating Water.

1.2.13 2104-1.6, Intemediate Cooling System.

1.2.14 2106-2.1, Condensate System.

1.2.15 2104-5.1, Reactor Building Nomal and Emergency Ventilation.

1.2.16 2104-1.7, Penetration Cooling.

1.3 Manufacturers' Instruction Manuals.

1.3.1 Diamond Power " Control Rod Drive Mechanism Control System" instruction manual Volume I and II 0115-02 and 01-0116-01.

1.3.2 Bailey Meter Company " Integrated Control and Non-Nuclear Instrumentation System" instruction manual Volume 1A, Volume 1B and Voli me 2.

1.3.3 Babcock & filecx, " Physics Test Manual", TMI-2.

TG 06-000-23.

1.3.4 Westinghouse, " Steam Turbine for Jersey Central Power & Light Unit 2" Instruction Book Volume I (I-B-NO-1250-C734).

1.3.5 Westinghouse " Hydro Inner Cooled Turbine Generator for Jersey

)

Central Power & Light Unit 2" Instruction Book (I-B-NO-20792) 1.4 Applicable System Descriptions.

1.4.1 Not Applicable.

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05/04/78 1.5 Curves, Figures, Tables, etc.

AFh 2 3 1375 1.5.1 Curves.

Figure 1 - Core Pressure / Temperature Safety Limits.

Figure 2 - Operational Power Imbalance Envelope (0-200 EFPD)

Figure 3 - Control Rod Group Withdrawal Limits for 4 Pump Operation (0-200 EFPD).

Figure 4 - Control Rod Group Withdrawal Limits for 3 Pump Operation (0-200 EFPD).

Figure 5 - Control Rod Group Withdrawal Limits for 2 Pump Operation (0-200 EFPD).

Figure 6 - Control Rod Group Designation and Core Position.

Figure 7 - Reactor Coolant System Pressure / Temperature Limits for Heatup and Cooldown and Core Criticality.

Figure 7A - Heatup/Cooldown Curve.

Figure 8 - Minimum Boric Acid Tank Contained Volume / Concentration.

Figure 9A - Core power vs. Rod Position Bands 4 Pump Operation (0-200).

Figure 9B - Core Power vs. Rod Position Bands 3 Pump Operation (0-200 EFPD).

Figure 9C - Core Power vs. Rod Position Bands u Pump Operation (0-200 EFPD).

Figure 10 - Borate /Deborate + 10% Rod Position (BOL-140 EFPD).

Figure 11 - RC Boron Change Needed to Reposition Rods in Bands.

Figure 12 - Mini.num Feed and Bleed Flow Rate per Load Change vs. RCS Boron Cori:entration.

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Figure 13 - Pressurizer Level vs. T-ave.

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Figure 14 - Shutdown Baron Concentrations vs EFPD.

1.5.2 Tables.

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Table 1 Quadrant Power Tilt Limits.

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$k-Table 2 DNS Margin.

AFA 2 3 7979 1.5.3 Appendix.

1.

Surveillance Requirements Modes 3 to 2.

2.

Surveillance Requirements Modes 2 to 1.

3.

Mechanical Maneuvering Recomendations.

2.0 LIMITS AND PRECAUTIONS 2.1 Equipment.

2.1.1 When operating letdown coolers, intermediate cooling pumps, and intermediate coolers must be in operation.

2.1.2 When increasing reactor coolant temperatures greater tnan 532 F, monitor turbine throttle pressure to insure the turbine bypass valves maintain proper throttle pressure.

2.1.3 Do not attempt to start a Reactor Coolant Pump when power is greater the 30%.

2.1.4 The pressurizer spray valve minimum bypass flow must be maintained

(.,1 gpm).

2.1.5 For normal plant heatup and cooldown conditions the maximum delta T batween the feedwater line temperature and steam generator lower downcomer temperature is 440 F when using the main feedwater nozzles.

2.1.6 With a filled and vented RC System, do not fill, drain, or blow an OTSG dry withoet flow in the RC System.

Flow may be through Decay Heat or RC Pumps.

Rate of fill, drain, or blowdown shall nnt decrease o.C System temperature (T-cold) or OTSG downcomer temperature by more than 50 F below initial 0

1 temperature.

2.1. 7 Maximuh. allowable OTSG fill rate is 500 gpm per S.G.

2.1. 8 Maximum allowable AT between RCS and OTSG average shell temperature 0 217 is 60 F.

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2.1.9 "During startup and shutdown, when reactor average temperature 0

is 525, OTSG mter level shall ce maintained between 97 and 99 percent on the ope c. ting level instrumentation. This is done to ensure ficoding of tna feedwater no::les and reduce circurt.ferential thermal gradient cycles on the feedwater nozzles during Mode 3.

Prior to entering Mode 2 OTSG water level shall be steamed down to the low level limits."

2.1.10 The Nuclear Instrumentation will be continuously monitored during any reactivity addition. During withdrawal of control rods, subcritical source multiplication will be confirmed according to the following equation or the startup will be teminated until an appropriate evaluation is raade.

N

SDM1 (100 - SDM2)

SDM2 (100 - SDM1) where M = Multiplication factor SDM1 = Shutdown Margin prior to reactivity (% ak/k)

SDM2 = Shutdown Margin after reactivity (% ak/k)

NOTE:

SDM1 and SDM2 are negative valves.

2.1.11 During withdrawal of safety rods, a 1/M vs Rod Position Plot will be maintained to insure criticality is not achieved.

2.1.12 Do not exceed 2772 MWt (Core Themal Power).

2.1.13 Maintain power below the p0wer level cutoff (See Figures 3 and

4) until the xenon reactivity is within 10 percent of the equilibrium value for operation at rated power and approaching stability or THERMAL POWER has been within a range of (87) to

)

(92) percent nf RATED THERMAL POWER for a period exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in the soluble poison control mode, excluding xenon free start-ups.

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AFR 2 3 1379 NOTE:

Determine Xenon reactivity using either SP 2311-4 or ccmputer program ROBAL.

2.1.14 Monitor core power distribution with in-core detectors and the on-line computer as follows:

During steady-state operating, a 3-D Power Map (Group 34) and a worst case Thermal Condition (Group 20) data dump should be taken every EFPD. The reactor power level, be on concentration, and core burnup should also be recorded. This data should be collected each day at midnight along with the Station Daily Log Sheet, Heat Balance (Group 32), Reactivity Balance (Group

22) and Periodic Typewriter Log Daily Sumary for delivery to the Station Nuclear Engineer.

2.1.15 Following a significant one-step load change (> 10% rated pcwer) above 50% rated power or significant control rod motion

(> 10% insertion or withdrawal) a Worst Case Thermal Condition should.)e taken within one hour after the change and then every 4 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for a period of 24 to 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months , or longer if evice ice of a power distribution transient exists. A 3-D Power Map should be taken aoout 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reaching steady-state conditions. These data printouts are not necessary on the way up to full power if the Mechanical Maneuvering Recomendations are followed. However, the data from Groups 20 and 34 should be called out one hour after the power hold level is reached.

2.1.16 Obtain a 3-D power map whenever a large imbalance or any other

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Revision 5 2.1.17 When operating from 50 to 100% rated power with 4 RC pumps 02/10/78 running, maintain cold leg differential teraperatures less than 5 F.

During load transient near rated power maintain cold leg U

differential less than 10 F.

NOTE:

With less than 4 RC pumps running the cold leg temperature may exceed these limits but not over U

20 F.

2.1.18 Maintain all control rods and axial power shaping rods within

+ 6.5% (indicated position) of their group average height (T.S. 3.1.3.1).

2.1.19 Except for physics tests or exercising control rods, the control rod insertion / withdrawal limits are specified on Figure 3, Figure 4 and Figure 5 for various RC pump combinations.

If the control rod position LOCA limits are exceeded, proceed with T.S. Action Statement 3.1.3.7.

If the control rod position Shutdown Marcin limits are exceeded, proceed with T.S. Action Statement 3.1.1.1.

2.1.20 Canauct surveillance testing as listed on the surveillance test schedule in accordance with Administrative Pmcedure -

1010.

2.1.21 Maintain shift logs in accordance with Administrative Procedure -

1012.

2.1.22 Maintain pressurizer level within the limits of Figure 13.

2.1.23 Do not feed steam generators via auxiliary feed no::les except during emergency conditions or unless feedwater temperature is j

within 50 F of bcth RC System and 0TSG t hell; however, the j

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4 auxiliary feed nozzles must be used or filling an empty OTSG (< 10

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inches startup level) when RC temperature is above 200 F.

2.1.24 Maintain rakeup tank level above the low level alam.

2.2 Administra tive.

2.2.1 During reactor startup do not exceed a stable startup rate of 1 DPM, the prompt change associated with this rate should be less than 1.5 DPM.

2.2.2 Do not exceed a reactor coolant heatup rate of 100 F/hr.

2.2.3 Do not load the turbine at a rate in excess of the recommended loading rate in 2106-3.1.

CAUTION: Do not exceed MMR listed in Appendix 3.

2.2.4 The reactor control rod position and baron concentration shall be maintained such that an available shutdown margin of at least 2% ak/k if k eff > l.0 or 1% a k/k if k eff <l.0 exists with the single most reactive rod stuck out (T.S. 3.1.1.1).

2.2.5 On annunciation of an Asymmetric Fault on Control Rod Drive, verify the status of the rods in the group. All control rods should be operable and positioned within 9 inches (+ 6.5%

indicated pocition) of their group average height. The misaligned rod is declared inoperable and power operation of the reactor would be restricted per T.S. 3.1.3.1.

2.2.6 If any Safety Limit (defined in Technical Specification 2.1 and 2.2) is exceeded, the Shift Superviscr til notify the Station / Unit Superintendent. The reactor shall be placed in HOT STANDBY within one hour. The licensee shall notify the f

Comaission, review the matter and record the results of the review, including the cause of the condition and the basis for 190 223 9.0 W,'

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06/22/77 I3 corrective action taken to preclude reoccurrence. Operation shall noti be resumed until authorized by the Commission.

2.2.7 If, during operation, the autcmatic safety system does not function as required, the Station / Unit Superintendent shall be no tified. The Shift Supervisor shall take appropriate action as outlined in the Tech. Specs. The reporting requirements of T.S. 6.9 shall be followed. Note that this appropriate action may include shutting down the reactor.

2.2.8 When a Limiting Condition for Operation (LCO) (defined in Section 3 of the Technical Specifications) is not met, the Shift Supervisor shall notify the Station / Unit Superintendent.

The reactor shall be placed in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months unless corrective measures are completed that permit operation under the permissible ACTION statements for the specified time interval as measured from initial discovery. The reporting requirements of T.S. 6.9 shall be followed.

2.2.9 Quadrant tilt shall be monitored on a minimum frequency of once every twelve (12) hours during power cperation above 15%

of rated power. T:le QUADRANT p0WER TILI shall not exceed the limits listed in Table 3.2-1 of Tech Spec 3.2.4.

(Table 1.5.2.1 attached).

2.2.10 When reactor power is less than 10% Fp, do not request a printout of the following computer :jroups:

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20 Worst Cast Thermal Condition MR 2 3 mg 31 Fluid Condition.

38 Core Average Therral Candition.

39 Core Map Themal Condition.

40 All Themal Output 53 belected Assembly Thermal Condition 2.2.11 AXIAL POWER IMBALANCE shall be maintained within the limits shown on Figures 3.2-1 and 3.2-2 of Tech Spec. 3.2.1 (Figure 2 attached). The AXIAL ?OWER IMBLANCE shall be determined to be within limits at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when above 40% of RATED THERMAL POWER except when an AXIAL POWER IMSALANCE (cceputer alarm package) monitor is iroperable, then calculate the AXIAL POWER IMBALANCE at least once per hour.

2.2.12 If axial power imbalance. e.needs the limits specified, restore the axial imbalance within limits in 15 minutes or be in HOT STANDBY condition within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

2.2.13 The Regulating Rod groups shall be limited in physical insertion as shown on Figures 3.1-2, 3.1-3, 3.1-4, 3.1-5, 3.1-6 and 3.1-7 of Tech Specs, with a rod group overlap of 25 + 5%

between sequential withdrawn groups 5 and 6/7.

(T.S. 3.1.3.7).

With the regulating rod groups inserted beyond the LOCA insertion limits, proceed with T.S. Action Statement 3.1.3.7.

With the regulating rod groups inserted beyond the Shutdown

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Margin limits, proceed with T.S. Action Statement 3.1.1.1.

4 2.2.14 The approval of the Shift Supervisor, Radiation Protection Supervisor, and Unit / Station Superintendent, must be obtained if maintenance or extended inspections must be perfomed within the secondary shield, on top of the "D" Rings, br?G 2 2 5

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08/22/78 APR 2. mg the reactor head area when the reactor power is greater than 1%.

Reactor power must not be increased until such work is completed or the situation is re-evaluated and further approval is obtained from the Radiation Protection Supervisor, Shift Supervisor, and Unit / Station Superintendent.

2.2.15 Observe the maneuvering rate limitations as listed in Appendix 3.

(Mechanical Maneuvering Recommendations). Refer to Appendix 3 for the appropriate power maneuvering recomendations prior to increasing power.

2.2.16 Following a Refueli g Per.:d, Startup, 'r similar operational occurrence which could alter 1.ne mixture of radionuclides in the reactor coola..., m analy.:ic far ino'vf Jwl gamma emitters should be perfort Ed 5 15

'dar:er vacuum pump discharge.

2.2.17 Power operation sitt. v. 't >-t av #dle reactor coolant pump is restricted to 4 tour

' hun having changed the RPS Setpoints.

If the reactor is nt r.'Jrneu to an acceptable RC pump operating combination at the end of the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period, the reactor may be operated at restricted power level defined in Tech Spec 3.4.1.

2.2.18 As a condition to the operating license, operation in modes 1 and 2 with less than th ee RC pumps operation is not oemitted.

2.2.19 Two Intemediate Range Neutron Flux and Rate Channels shall be OPERABLE prior to entry into Mode 2 and during reactor criticality, in accordance with Tech Spec. 3.3.1.1, Table 3.3-1.10.

f NOTE:

For Physics Testing the Intermediate Range detector can be connected to the reactimeter efter Reactor Criticality.

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2.2.20 Entry into Mode 1 (>5% FP) is not permissible until Two Intermediate Range Neutron Flux and Rate Channels are OPERABLE, in accordance with Tech Spec. 3.3.1.1, Table 3.3-1.10.

NOTE,:

For Physics Testing, an Intermediate Range detector may be connected to the reactimeter after Entry into Mode 1.

3.0 PRERECUISITES NOTE:

Appendix 1 & 2 (Mode Change Surveillance Requirements) may be commenced prior to meeting these prerequisites.

Initial Each Step Upon Satisfactory Completion.

0 3.1 Reactor coolant temperature is greater than 525 F.

3.2 Reactor coolant pressure is within the normal operating band of 2155 _+ 50 psig.

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Revision 1 06/22/77 3.3 The Integrated Control System (ICS) control stations are in one of the below listed conditions:

A.

Startup from a shutdown of greater than 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s:

All ICS stations are in hand and set in accordcance with 2105-1.4 except the turbine bypass valves.

B.

Startup from a shutdown of less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

All ICS stations are in hand except the turbine bypass valves and the startup feedwater valves.

3.4 One feed pump is in operation in accordance with 2106-2.4.

3.5 The Shift Supervisor will specify the boron concentration for startup.

NOTE:

Prior to deboration, the control rods should be withdrawn to rod index limits.

3.6 The following applicable prerequisite applies to startups following a reactor trip:

A.

For a startup following a reactor trip the cause of the trip must have been corrected, and an investigation into the circumstances must have been conducted and it must have been determined by the Station / Unit Superintendent that reactor operations can proceed safely.

B.

In the case where the cause of the reactor trip is undetermined following a detailed investigation, the reactor may be restarted with concurrence from the Station / Unit Superintendent upor successful completion of the reactor

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4 protective system tests listed in the Appendix 1, Mode 3 to 2 and Mode 2 to 1 Surveillance Checklists, prior to reactor startup.

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12/23/78 UIS 3.7 The turbine header pressure setpoint set at 47.5% (885 psig).

3.8 The ICS rate of change controller is set at 0%.

NOTE:

For operations below fiva percent power, maintain the OTSG'S on the low level limits while maintaining flow thru the feedwater nozzles by throttling FW-V-66A/B.

Use the turbine bypass valves for heat removal.

3.9 The pressurizer level setpoint is set at 100".

3.10 Source range (cps) and intermediate range (amps) indication available on strip chart recorder located above Panel 4.

If the recorder is inoperable, startup may continue with the Shif t Supervisor's permission.

3.11 The Tolicwing prerequisites apply to Reactor Building inspection prior to plant startup.

a.

VERIFY Containment Integrity has been established per 2311-5.

b.

Verify all personnel have left the Secondary Shield area of the Reactor Building.

c.

Insure all entrances into the Secondary Shield have been locked, barricaded, and labeled with the appropriate Radiation Signs.

c.1 East (D) ring 282'6" level.

c.2 West (D) ring 282'6" level.

c.3 R.B. sump area 282'6" level.

c.4 Grating over crawl space opening 282'6" level.

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c.5 RCDT room 282'6" level.

c.6 East (D) ring 347'6" level.

c.7 West (D) ring 347'6" level.

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d.

Verify all personnel have lef t the Reactor Building.

APR 2 3 1979 e.

Announce the following two times before exit of the Reactor Building, " Attention, all personnel. The Reactor Building is now being locked".

f.

Insure that all personnel and emergency access hatches have been locked, and the key is returned to the Shift Supervisor.

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3.12 Verify the curbine lube oil system is in operation and the APR 2 3 n7g

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turbine is on turning gear, per 2106-3.2 and 2106-3.1.

3.13 Verify sealing steam flow is established to feedwater pump turbines and main turbine-generator seals.

3.14 Verify a minimum of 25 inches Hg vacuum exists in Cold and Hot condenser. (2106-2.3).

3.15 Verify condensate and feedwater system is aligned for cleanup and heatup. Piace the turbine plant chemical addition system in operation per 2106-2.8.

3.16 Mode 4 Checklist in Heatup Procedure.

3.17 Verify that the coolant radwaste system is lined up per 2104-4.1 and 2104-1.2.

Verify that the Reactor Coolant Bleed Holdup Tanks, WDL-Tl A/lB/1C have sufficient capacity for reactor coolant expansion and deborating volume.

3.18 Verify reactor coolant Chemistry Sampling System is lined up and in service per 2104-1.11.

3.19 Verify the letdown and purification makeup system is in service in accordance with 21 04-1.2.

Establish the letdown flow at 45 gpm.

NOTE:

Do not reduce seal injection flow to less than 6 gpm/ pump et any time. Norral flow is 8 to 10 GPM/ pump.

3.20 Verify RC System Chemistry is within the requirements of 1800.?, also verify Feedwater/ Condensate Chemistry is within the specifications of 1800.3.

3.21 Three or more RC pumps are in operation.

2 4.0 PROCEDURE Initial Each Step Upon Satisfactory Completion.

190.21h.

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!I d

2102-1.3 Revision 10 n

a 09/27/78 j

4.1 Normal Unit Startup.

4.1.1 Complete Appendix 1 Checklist from Mode 3 to Mode 2).

_ _ _4.1.1.1 Complete 2311-3 Rod Pa Surveillance Data Sheets 2, 3, and 4 and lock the:abinets imediately prior to entering Mode 2.

4.1.2 Verify appifcable prersites are complete and the RCS is new at Hot Standby ct. ion (Mode 3).

The reactor has > 1 'k available shutdown margin.

a.

b.

RCS Tave > 525 F.

RCS pressure is being strolled at 2155 psig.

c.

d.

Turbine bypass valves automatic and controlling OTSG pressure at 885 p:.

"0TSG levels being conttled at the low level limits."

e.

4.1.3 Ensure that:

High Load Limit is set t 96.2.

a.

b.

Low Load Limit is set to 0.

Load Rate of Change is set to Mechanical Maneuvering c.

Recommendations of Appendix 3.

d.

Set Turbine Header Pressure to 47.5% (885 psig).

(Pre Req 3.7).

At Reactor Master Demand Station set Tave setpoint e.

0 to 582 F.

f.

The Steam Generator load Ratio ATc is on Manual and set to zero error).

~,

g.

Unit Master Hand / Auto station is on Manual and set b

to zero demand.

16.0 190-232_. r :

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=

y 2102-1.3 f

1 Revision 12 01/31/79 h.

Steam Generator / Reactor Master Hand / Auto station is j

on Manual and set to zero demand.

APR 2 3 gg i.

Reactor Master H/A station is on Manual and set to zero demand.

j.

Both Feedwater Cemand H/A stations are on manual with demand set to zco.

k.

Both Main Feedwater valves H/A stations are on Manual with demand set to zero.

1.

Both SU Feedwater Valve H/A stations are in manual and maintain OTSG's level on the low level limits.

m.

Both Emergency Feedwater Valve H/A stations are on

. Panual with demand set to zero.

n.

Both Feed Pump Speed H/A stations are on Manual with demand set to zero.

4.1.3.1 Verify both Intemediate Channels operable and not feedin! the reactimeter.

4.1.4 Verify that condensate and feed system is lined up and operational in accordance with 2106-2.1 and 2106-2.4.

4.1.5 Obtain pemission from the Unit 2 Superintendent, er his designee and take the reactor critical in accordance with

" Approach to Criticality" 2102-1.2.

CAUTION: Do not exceed a stable startup rate of 1 DPM.

4.1.6 Stablize the reactor 10-8 amps on the Intemediate Range, when the reactor is stable at 10-0 amps with zero startup rate, record criticality data; Baron PPM, RCS temperature, j

control rod position and time /date in the Control Room Log Book.

17.0 I!., 0 ~[f[

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2102-1.3

~3 Revision 1

?

06/22/77

?

APR 2 3 ggy9 4.1.11 Reactor Coolant will expand as the reactor coolant system heats up. Adjust letdown flow as necessary to maintain pressurizer level setpoint as indicated on Figure 13.

Divert letdown flow as necessary to maintrin the makeup tank level within its normal range in accordance with 2104-1.2.

Increase pressurizer level setpoint as indicated on Figure 13, as RCS temperature increases.

NOTE:

a)

MU-V17 minimum flow must be 9 gpm for valve protection.

b)

MU-V5 minimum flow must be 10 gpm for valve protection.

c)

As the reactor coolant system expands with the temperature increase, MU-Vl7 will close and makeup level wit' incraase.

4.1.12 After the Neutron power is stabilized, place the Diamond Rod Control Station in Auto as follows:

a.

Verify Neutron Error is < + 1% at Panel 4 meter.

b.

At the Reactor Master H/A station: place the "MV-POS" switch in "POS" and read manual Reactor demaild.

It should read approximately 5% corresponding to the neutron power.

(With Bailey and Diamond in Hand, Rx master tracks neutron power).

c.

Place the Diamond Rod Control station in Auto, if desired, by depressing the Auto pushbutton until the Auto light on Diamond Control Panel is illuminated.

}

The Reactor Master " Auto" light will go out as 4

Reactor Master is reverted to Manual.

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2102-1.3 Revision 13 03/14/79 1t,Zj 4.1.13 If applicable, observe Feedwater flow rate at five percent APR 2 * $7d power (it should be = 200,000 lbs/br OTSG). Maintain this flow rate manually and at the Reactor Master H/A station use the Raise-Lower switch to gradually increase power to approximately 10%. This will cause the OTSG's to come off the low level limits.

CAUTION:

Increase power at a rate which does not exceed a maximum heatup rate of 100 /hr (T.S. 3.4.9.1).

NOTE:

When altering the Steam Generator level, do not allow Tave to get out of specs per 2101-1.1, Limits and Precautions, Figure 1.0-07.1.

4.1.14 When Steam Generator level is at the low level and observed feedwater flo'.< rate is at approximately 200,000 lbs/hr, If not already done place the corresponding Startup feedwater valve in AUTO by the following steps:

a.

Shut FW-V66A/B prior to placing the associated startup feedwater valve (FW-V25A/B) in AUTO.

b.

Place the "MV-POS" switch to startup feedwater valve

( FW-V25A/B) to "MV".

When the MV-POS indicator is on the red diamond, place the startup feedwater valve in Auto by depressing the Auto pushbutton and holding it until the Auto light is lit.

c.

When the level on the second OTSG is at the low level limit & feedwater flow is approximately 200,000 lbs/hr, repeat step (a & b) for the corresponding startup feedwater

~

valve.

a 4

d.

With th-Bailey controller for Main FW valves, FW-V30A and FW-V308, in MANUAL:

20.0 19 0-_M5e

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J 3, 2102-1.3 i

Revision 10

?

i 09/27/78 4.1.7 Ensure letdown coolers are in service in accordance with

]

2104-1.2.

APR 2 3 ;g79 CAUTION: Do not exceed a reactor coolant heatup rate of U

100 F/hr.

If both letdown coolers are not in operation, limit heatup rate as required to remain within the heat removal capacity of the available letdown cooler.

4.1.8 Verify that prerequisites of Turbine Generator Operating Procedure 2106-3.1 are met and the 500KV substation is aligned by turbine roll per 2107-1.3, Section 4.6.2 CAUTION: Insure that the Turbine Trip Bypass Switch on Panel 18 is locked in the Normal position prior to closing B2-06.

4.1.9 Complete Appendix 2, (Mode 2 to Mode 1 Surveillance Checklist).

4.1.10 Using Diamond Rod Control increase power to approximately P

5% neutron power while maintaining OTSG levels on the low level limits.

NOTE:

Following any thermal power change of more tnan 15% of rated thermal power within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, notify HP/ CHEM that primary coolant must be sampled and analyzed for Iodine (including I-131, I-133 and I-135) between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following the change per 2304-3D2. This isotopic analysis of the primary coolant shall continue y

at 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months intervals until the specific activity

.f drops below 1.0 pCi/gm dose equivalent I-131 or 100/E uCi/ gram (T.S. 4.4.8).

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R 2 3 7379 Revision 13 5

03/14/79 1.

Insure corresponding Main FW block valves, FW-V14A and FW-V148, are closed by visual inspection.

2.

Stroke FW-V30A and FW-V3CB with the Bailey controller and visually verify valve movement.

3.

Af ter stroking P4-V30A and FW-V30B, with FW-V30A and FW-V308 visually verified closed; place the Main FW valves, FW-V"0A and FW-V308, in AUTOMATIC per step (b) abose.

4.1.16 Place Loop A and Loop B Feedwater Demand H/A station in Auto by the following procedure:

a.

Place the "MV-POS" switch to "POS" on both Loop A and Loop B Feedwater Demand Stations and verify that the manual demand from each station is 0%.

b.

Place the "MV-POS" switch to "MV" on both Loop A and Loop B Feedwater Demand Stations.

Read the error between Auto and Manual Feedwater Demand. Both static.is should read 50% (zero error), if not, use the applicable procedure below to balance the Feedwater Demand Stations:

1)

If both Feedwater Demand Stations indicate an equal error on the MV-POS Indicator, use the SG/Rx Master H/A station " Raise-Lower" switch and adjust SG/Rx demand until both feedwater Demand Stations indicate 50% (zero error).

NOTE:

Feed pump speed control will be i

maintained using valve position or

~~

limiter R..ise/ Lower switch on Panel 5

~

1?0...,yy:

2' o o

yy 2102-1.3 f

APR 2 3 1379 Revision 13 03/14/79 until 35% RP.

Maintain AP,of at

]

least 35 psi across FDW Control valves A and B.

2)

If the Feedwater Demand Stations indicate unequal errors, use the Steam Generator Load Ratio a Tc H/A station " Raise-Lower" switch and adjust a Tc error until both Feedwater Demand errors are equal, then repeat step (1) above.

c.

Place the "MV-POS" switch in "POS" on Loop A Feedwater Demand H/A Station.

d.

Place Loop A Feedwater Demand H/A Station in "AUT0" by depressing the "AUT0" pushbutton until the "AUT0" light is lit.

e.

Repeat steps e and d above for Loop B Feedwater Demand.

4.1.17 Place the SG/Rx Master H/A station on AUTO as follows:

a.

At the Steam Generator / Reactor Master H/A station place the MV-POS switch to MV, Meter should read 50%

(Zero Error).

b.

At the SG/Rx Master H/A Station, place MV-POS switch to POS and depress the Auto pushbutton until the Auto Lamp on the station is illuminated.

CAUTION (1):

Do not exceed a reactor coolant U

heatup rate of 100 F/hr or the capability of the available letdown flow.

f CAUTION (2):

Do not exceed the power increase rate j

of 10% per hour until 20% power (Mechanical Maneuvering Recommendations).

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v 2102-1.3 f

~ APR 2 a ISl9Revision 13 i

03/14/79 NOTE:

If Diamond Rod Control Station is not in AUTO, place in AUTO per step 4.1.12.

4.1.18 At the Reactor Master H/A station, with the MV-POS switch in "POS" reading manual reactor demand, use the Raise-Lower switch and increase power to approximately 12-14%

neutron power.

4.1.19 Align the extraction steam and feedwater heeter vents per 2106-1.2A.

4.1.20 Bring the Turbine to Synchronous speed in accordance with 2106-3.1.

CAUTION: Turbine Bypass Valves should maintain Turbine header pressure @ setpoint.

4.1.21 Notify the dispatcher and proceed to synchronize the generator in accordance with 210f-3.1. On eutematic synchronization, the turbine should pick up = 5% of full load, = 48 MWe.

NOTE:

Follow recommended startup and loading times curve, Figure 5 of 2106-3.1.

CAUTION: Do not exceed the power increase rate of 10%

per hour until 20% power (Mechanical Maneuvering Recommendations).

4.1.22 Raise the Turbine load as follows:

a.

With the Turbine in "0PER AUT0", set the setter to 150 MW by pressing Raise button.

~

b.

Set the load rate per 2106-3.1 at 1.6 MW per minute.

c.

Press IMP IN button.

23.0

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2102-1.3 M

Revision 13 i

7 03/14/79

(

d.

Press "G0" button.

APR 2 3 7379 NOTE:

As turbine lead increases, megawatts generated increase, thereby, the Unit Load Demand increases.

4.1.23 Observe the Turbine Bypass valve (MS-V25A, MS-V25B, PS-V26A, and MS-V26B) close gradually as Turbine Generator picks up the load. As Turbine Bypass Vahes close completely, indicated by Zero (G) Demand on H/A Station press "0PER ICS" button and place the Turbine in Integrated Control Mode. Verify " Main To:oine on Manual" alarm is cleared, and ICS is no knger in track.

4.1.24 Start one Heater Drain Pump and align the feed heaters per 2106-1.2.

4.1.25 At the Reactor Master H/A Str.: ion with the MV-POS switch in "POS" reading manual ?r. actor Demand, use the Raise-Lower switch and increase power to 15% FP.

4.1.26 After the power is stabilized, place the Reactor Master H/A station in AUTO by the following procedure:

a.

Place the "MV-POS" swi :h to "POS" and verify that the manual Reactor De: rand is approximataly 15%.

b.

At the Reactor Demand Station, place the MV-POS switch in "MV" and ready Tave error.

It should be 50% (zero error), if not, use the Tave sevoint knob and adjust the Tave error to 50% (zero error).

c.

Place the "MV-POS" switch to "POS".

2' d.

Place the Reactor Master H/A station to AUTO by j

depressing the Auto pushbutton until the "AUT0" r

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f 2102-1.3 APR 2 3 ggRevision 13

?

03/14/79 light is lit.

"The Reactor Master Station on Manual"

]

alarm will clear.

e.

Using the Tave setpoint knob, slowly adjust the Tave to 62% (582 F).

4.1.27 Now reactor, steam generator and turbine generator are in integrated mode, except for FWPS control and the unit load is controlled by the Unit Master in " Hand".

4.1.28 With the unit load stabilized at 15% of FP (=150 MWe) collect the following operating data from Plant Computer.

1.

Quadrant Power Tilt.

Verify Quadrant Power Tilt is within limits of Tech Spec 3.2.4.

NOTE:

While operating above 15% FP get Quadrant Power Tilt printout frcm Plant Computer every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.1.29 Notify Load Dispatcher and with his concurrence raise power to 20%, by establishing the Unit Load Demand approximately 19.2%.

CAUTION 1:

Do not exceed the power increase rate of 10 percent per hour until 20 percent FP (Mechanical Maneuvering Recommendation).

CAIJTION 2:

Maintain Control Rods in the Transient Rod Position Band (Figure 9A, 93, or 9C) per

?102-2.1.

Guidance on the transition from startup Feedwater Regulating j

Valve Control to Main Feedwater Regulating Valve Control.

f CAUTION:

Insure the Control Rods are in the Transient Band.

25.0'

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i

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2102-1.3 Revision 13 I

APA 2 3 03/14/79 3 79 Power level should be set to give 60 to 70% open on the Startup Feedwater Regulating Valve with approximately 80 psid across the valve. Bring Feedwater Valve AP to 35 psid and place the Feedpump in AUTO. This should force the Startup Feedwater Regulating to exceed 80% open position and hence open the Main Feedwater Block Valve.

The Main Feedwater Regulating Valve should open to about 20% position.

If necessary, increase power level to maintain the Main Feedwater Regulating Valve open. The Startup Feedwater Regulating Valve may be placed in Hand to maintain it open while power level is increased.

4.1.30 When both steam generators lift off the Low Level Limit and SG Low Level Aalrm is cleared, place the steam generator load r atio ATc H/A station in "AUT0" by the followins prvcedtre:

a.

Place the "MU-POS" switch to "MV" and read ATc error.

It should read 50% (zero error).

If not, use the ATc setpoint and adjust ATc error to 50%

(zero error) on MV-POS Indicator.

b.

Set the "MU-PO5" switch "POS" and place the Steam Generator Lord Ratio ATc H/A station in Auto by depressing the "AUT0" pushbutton until the Auto light is lit.

4.1.31 Secure feedwater heating by Aux Steam per 2106-1.2, Section 4.1.

j 4.1.32 After the unit load has stalilized at 20% (192 MWE),

ensure the following Turbine Drai.ns are closed as indicated 26.0

. S s'&=,

_ ~ _ _.

JO.

iAl I

7' 2102-1.3 I

Revision 13 4FR 2 3 9g03/14/79 on Panel 17: MS-V281 A & B; MS-V282A & B; MS-V283, MS-

~

V284, MS-V285A & B andMS -V286A & B.

If above valves are not closed use MS-FHS-4*.74 to close the valves.

NOTE:

If reactor is operating with less than four (4)

RC pumps, check for down pump availability and if available start non-operating pumps per 2103-1.4 before 30 percent powar.

Reset Nuclear overpower trip RPS setpoints for operating pump combination as p?- 2311-6.

4.1.33 5-: art the second condensate pump, condensate booster pump aad place the third condensate pump and condensate booster pump pair in standby.

Notify Load Dispatcher and with his concurrence raise power to 35%, by establishing the unit load demand at the unit master to approximately 33.6%.

CAUTION 1:

Do not exceed the power increase rate of 30 percent per 'our (Mechanical Maneuvering Recommandation).

CAUTION 2:

Maintain control rods in the transient rod band (Figure 9) per 2102-2.1.

4.1.34 After the unit has stabilized at 35% load (336 MWE),

start the timed opening of the Second Stage Reheater Control valves in accordance with 2106-3.1.

4.1.34.1 Prior to exceeding 30% power, place the control switch for T-56-2, 2A-3.2_(28-32), 2A-42 (28-42) in pull-to-lock I

position. The 4160V bus MV is read from the KW meters and adding the reading together.

24}.

f 27.0 e

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3 2102-1.3 Revision 13 I

03/14/79

~

a.

ZA-32 (2B-32) KW b.

2A-42 (2B-42) KW c.

2A-62 KW (T-56-2) d.

2B-52 KW (T-56-2) e.

2A-TE2 (2B-lE2) KV f.

2A-2E2 (28-2E2) KW This insures adequate voltage levels at the 480V ESF busses, in the event of a loss cf an Aux. transformer.

4.1.35 Notify the Load Dispatcher and with his concurrence raise power to 40% FP, by establishing the Unit Load Demand to approximately 38.4%.

CAUTION 1:

Do not exceed the power increase rate of 30 percent per hour (Mechanical Maneuvering Recommandation).

CAUTION 2:

Maintain Control Rods in the transient rod position band (Figure 9A, 98, or 9C) per 2102-2.1.

4.1.36 After the unit load has stabilized at 40% load (:84 MWE),

cel',ect the following operating data from Plant Computer.

1.

Heat Balance.

2.

Quadrant Power Tilt.

3.

Axial Power Imbalance.

Maintain Axial Core Imbalance by movement of APSR to remain within the limits of Tech Spec 3.2.1.

(Fig 2).

NOTE:

Monitor Core Imbalance on a minimum frequency of once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during power operation c 3'.

above 40% F.P.

/

28.0

'1 2 47 [

~

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2102-1.3 i

Revision 13 i

03/14/79 4.1.37 When Unit load has stabilized at 40%, (384 MWE), perform

~

tr.e following.

a.

CLOSE deaerating steam supply valves EX-V71 A and 71B.

b.

Ensure the casings for the non-running Heater drain pumps are floodea and vented.

c.

START a second heater drain pump by placing its Panel 5 control switch to START.

Ensure that suction /

discharge pressures, seal injection flow, running amps, oil pressure, and oil temperatures are normal.

d.

Place the third heater drain pump in STANDBY after verifying proper seal injection flow and oil levels by allowing its centrol switch handle (s) to return to NORMAL.

e.

Monitor moisture separator-reheater drain tanks, feedwater heaters, and the heater drain tank to ensure proper water levels 6re being maintained.

4.1.38 At 40% load START the feedwater pump in accordance with 2106-2.1 and 2106-2.4 respectively.

4.1.39 Place the second feedwater pump turbine in Auto as follows:

a.

Using the " Raise-Lower" switch, increase turbine speed until the discharge pressure of the oncoming Feed Pump Turbine is equal to the discharge pressure of the running pump as indicated by pressure gages j

on Panel 5.

b.

Increase the encoming Feed Pump Turbine speed slightly and observe that the running Feed Pump Turbine speed 29.0

.=

g0 245 i

2

h M.

APR 2 3 1979 2102-1.3 Revision 13 5

03/14/79 decreased as the Feed Water load begins to distribute itself between the pumps.

c, Place the MV-POS switch on the oncoming Fesd Pump Turbine in "MV" and read the error between Auto and ma'ual Feed Pump Turbine speed demand. Use the Raise '.ower switch and adjust the demand until the error is zero (50% on indicator). Check that the speed of the pump in A'!to decreases as the oncoming Feed Pump Tur 'ne assumes half of the Feed Water load.

d.

Place the oncoming Feed Pump Turbine in Auto by depressing the Auto pushbutton until the " Auto" light is lit.

e.

Using the bias control on Feed Pump Turbine "A",

adjust Feed Pump Turbine speeds until Feed pump "A" flow equals Feed pump "B" flow as indicated on Flow meters on Panel 4.

4.1.40 With the consent of the Load Dispatcher raise power to 72%, by establishing the Unit Load Demand to approximately 69%.

CAUTION 1:

Do not exceed the power increase rate of 30 percent per hour.

CAUTION 2:

Maintain Control Rods in the Tran::ient Rod Position Band (Figure 9A, 9B, or 9C) per 2102-2.1.

4.1.41 After the unit load has stabilized at 72% load (692 MWE) collect the following operating data from Plant Computer.

ffQ 30.0

?

APR 2 3 2',02-1.3 i

hevision 13 03/14/79 1.

Heat Balance.

2.

Axial Power Imbalance.

3.

Quadrant Power Tilt.

4.1.42 Hold the power steady for five (5) hours at = 72% F.P.

This 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months reactor power hold allows time for fuel pellet and clad creep to accomodate the differential thermal expansion and thereby minimizes the effects of pellet-clad interaction.

NOTE:

If the reactor has been at less than 20% FP for less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months power hold at 72%

power is not required.

4.1.43 With the consent of the Load Dispatcher raise power to 90 percent, by establishing the unit load demand to approximately 86.4 percent.

CAUTION: During the initial power escalation at cycle startup or immediately following a control rod interchange, the initial escalation above the 75% full power shall be limited to 3% per hour, with a five (5) hour hold at the power level

~

cutoff. This hold can run concurrent 1y with 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months hold required by Technical Specification 3.1.3.9.

NOTE 1:

For Normal power escalation do not exceed the Power Increase Rate of 30 percent per hour.

NOTE 2:

Maintain Control rods in the transient rod position band (Figure 9A, 93, or 9C) per 2102-2.1.

~41.0 l?0 2q

APR g 2102-1.3 0

2 Revision 13 03/14/79 2

4.1.44 After the unit load has stabilized at 90% load (864 MWE) collect the following operating data from Plant Computer.

1.

Heat balance.

2.

Axial Power Imbalance.

3.

Quadrant Power Tilt.

4.1.45 Hold the power steady for five (5) hours at =90% FP.

This 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months : eactor power hold allows time for fuel pellet anu clad creep to accomodate the differential thermal expansion and thereby minimize the effects of pellet-clad interface.

NOTE:

During N% Power Hold take 3-D Power Map 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after power is stabilized.

CAUTION: Prior to increasing Power greater than 92%,

requirements of Tech Spec 3.1.3.9 must be satisfied.

4.1.46 With the consent of the Load Dispatcher raise power to 100% FP, by establishing the unit load demand at approximately 96 percent.

CAUTION: During the initial power escalation at cycle startup or immediately following a control rod interchange, the initial escalation above the 75% full power shall be limited to 3% per hour.

NOTE 1:

For Normal Power Escalation do not exceed the power increase rate of 30 percent per hour.

NOTE 2:

Maintain control rods in the transient rod I

position band (Figure 9A, 93, er 9C) per 2102-2.1 during power escalation.

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2102-1.3 Revision 13 i

^#^

03/14/79

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TABLE 1 OUADRANT POWER TILT LIMITS STEADY STATE TRANSIENT MAXIMUM LIMI'.

LIMIT LIMIT Measurement Independent QUADRANT POWER TILT 3.69 9.74 20.0 QUADRANT POWER TILT as Measured by:

Symmetr' al Incore Detector System 2.30 7.71 20.0 Power Range Channels 0.96 5.88 20.0 Minimum Incore Detector System 1.72 3.71 20.0 7

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03/14/79 AFR 2 3 :37f APPENDIX 1 SURVEILLANCE REQUIREMENTS Appendix 1 data sheets list the surveillance requirements for ascention form Mode 3 to Mode 2.

a.

The INITIALS bicck for each requirement certifies that satisfactory data for the applicable Surveillance Procedure has beea collected within the time interval indicated in the SURV FREQ block and is available for audit, b.

The 0 ATE SP SATISFIED block shall contain the date of the last satisfactory performance of the applicable Surveillance Procedure.

c.

The NAME, DATE, TIME entries at the bottom of the MODE columns signify that surveillance requirement compliance has been verified and that entry may be made into the specified OPERATIONAL MODE.

d.

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Revision 13 7

03/14/79 APPENDIX 2 SURVEILLANCE REQUIREMENTS Appendix 2 data sheets list the surveillance requirements for ascention form Mode 2 to Mode 1.

a.

The INITIALS block for each requirement certifies that satisfactory data for the applicable Surveillance Procedure has been collected within the time interval indicated in the SURV FREQ block and is available for audit.

b.

The DATE SP SATISFIED block shall contain the date of the last satisfactory performance of the applicable Surveillance Procedure.

c.

The NAME, DATE, TIME entries at the bottom uf the MODE calumns signify that surveillance requirement compliance has been verified and that entry may be made into the specified OPERATIONAL MODE.

d.

When a Surveillance Procedure is established, the schedule of surveillance relevant to that procedure is a function of that procedure, the responsible supervisor and the Tech Spec Surveillance Program (AP1010).

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2102-1.3 Revision 13 '

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03/14/79

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APPEllDIX 2 tbde 2 to Mode 1 Page 1 of 1 DATE SP SURV.

RESP 0ti-SATISFIED IllITI ALS FREQ.

SIBILITY S.P. fl0.

T.S. fl0.

DESCRIPTI0fl 5,D OPS 2301-S1 REFER TO 2301-51 SilIFT Afl0 DAILY CilECKS

^

7 da OPS 2301-W1 REFER TO 2301-W1 WEEKLY CilECKS 18 mo.

IC 2302-R4 4.3.3.2 (b)

IfF.02 DETECTOR CilAN CALIB i

RCS TOTAL FLOW MEASUPEMEllT 18 mo.

OPS 2303-R4 4.2.5.2 (When at 100% RTP)

~-

il0TE 4.2.2.1 (b i,4.2.2.2 POWER DISTRIBUT10tl 31 da OPS 1

2311-F2 4.2.3.1 (bh,4.2.3.2 (When > 20% RTP)

ALL TECil SPEC REQUIREMEllTS FOR ENTRY INTO. MODE 1 ilAVE BEEli SATISFIED:

PERFORMED BY:

APPROVED BY:

DATE TIME DATE TIME F10TES:

1 Provisions of Tech Spec 4.0.4 Not Applicable.

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Revision 13 03/14/79 APPENDIX 3 f

MECHANICAL MANEUVERING RECOMMENDATIONS The following are the recomended maneuvering limits for TMI-2, Cycle 1:

1.

The maximum rate of power increase below 20% full power shall be 10% per hour.

2.

Above 20% power, normal operating procedures (Tech Spec 3.1.3.9) will apply unless the reactor has operated at less than 20% power for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

3.

If the power level has been below 20% full power for greater than forty-eight (48) hours, the maximum rate of power increase above 20% full pcwer shall be 30% per hour with a five (5) hour hold at 20% full pcwer below the power level cutoff and a five (5) hour hold at the power level cutoff. These holds can run concurrently with holds required by the Technical Specification.

4.

During the initial power escalation at cycle startup or imediately following a control rod interchange, the initial escalation above the 75% full power shall be limited to 3% per hour, with a five (5) hour hold at the power level cutoff. These holds can run concurrently with Technical Specification holds where applicable.

5.

With the exception of item 4 above, no restrictions are placed on required physics startup tests.

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190 264 58.0

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ML19224B180

Text

1.0 REFERENCES

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