ML19224B268

Operating Procedure 2102-3.1,Revision 8:unit Shutdown

ML19224B268
Person / Time
Site:	Crane
Issue date:	03/07/1979
From:	Metropolitan Edison Co
To:	Mullinix W NRC/IE
References
2102-3.1, TM-0403, TM-403, NUDOCS 7906140327
Download: ML19224B268 (43)

Text

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r C0'VT'R0w' ' :"D COPY -3 ' c, ^. - Revision 8 . CENTRAL F2E ~ THREE MILE ISLAND NUCLEAR STATION Ut1IT #2 OPERATI:1G PROCEDURE 2102-3.1 UNIT SHUTDOWN Table of Effective Pages Page Date Revision Page Date Revision Pace Date R evision 1.0 06/20/77 0 25.0 08/04/77 1 2.0 06/20/77 0 26.0 02/13/.78 3 3.0 06/20/77 0 27.0 02/13/78 3 4.0 04/18/78 4 28.0 02/13/78 3 4.1 04/18/78 4 29.0 06/20/77 0 5.0 12/23/78 7 30.0 04/18/78 4 6.0 06/20/77 0 31.0 06/20/77 0 7.0 06/20/77 0 32.0 04/18/78 4 8.0 02/13/78 3 32.1 04/18/78 4 9.0 06/20/77 0 32.2 04/18/78 4 10.0 02/13/78 3 33.0 06/20/77 0 11.0 0213/78 3 34.0 06/20/77 0 12.0 06/20/77 0 35.0 06/20'77 0 13.0 06/20/77 0 36.0 06/20/77 0 14.0 07/07/78 5 37.0 06/20/77 0 15.0 04/18/78 4 38.0 03/07/79 8 16.0 04/18/78 4 39.0 06/20/77 0 17.0 04/18/78 4 18.0 07/07/78 5 19.0 07/07/78 5 20.0 09/22/78 6 21.0 09/22/78 6 22.0 12/23/78 7 23.0 12/23/78 7 24.0 09/22/78 6 Unit 1 Staff Recommends Approval Unit 2 Staff Recommends Approval Approval I Date Approval 8 Date Cognizant Dept. Haad Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Rec mmends Approval [ Date 83 Date 5 f-Chairman of PORC \\/. Chairman of PORC 1 ~ Unit 1 Superintendent Approval Unit 2-Superintendent Approval Date 5b kY 5 MAW Date Y t Manager Generation Quality Assurance Approval 8[ Dht9 5 2 3 9 TMI SS-A R ev 8/77

I;' .l' 2102-3.1 5 Revision 0 06/20/77 THREE MILE ISLAND NUCLEAR STATION UNIT #2 OPERATING PROCEDURE 2102-3.1 UNIT 5HUTDOWN TABLE OF CONTENTS SECTION PAGE

1.0 REFERENCES

2.0 1.1 Drawings Applicable for Operation 2.0 1.2 Operating Procedures Applicable for Operation 2.0 1.3 Manufacturer Instruction Mancals 3.0 1.4 Applicable System Descriptions 4.0 1.5 Curves, Figures, Tables, etc. 4.0 2.0 LIMITS AND PRECAUTIONS 4.0 2.1 Equipment 4.0 2.2 Administrative 8.0 3.0 INITIAL CONDITIONS 12.0 4.0 PROCEDURE 12.0 4.1 Normal Unit Shutdown 12.0 e 1.0 195 240 ma m -.w.

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-?/ p' ~ 2102-3.1 Revision 0 06/20/77 THREE MILE ISLAND NUCLEAR STATION UNIT #2 OPERATING PROCEDURE 2102-3.1 UNIT SHUTDOWN

1.0 REFERENCES

1.1 Drawings Anplicable for Operation Main & Reheat Steam-8&R Drawing ik). 2002 Bleed Steam-B&R Drawing No. 2003 Auxiliary Steam-B&R Drawing No. 2004 Feedwater & Condensate-B&R Drawing No. 2005 Makeup Water Treatment & Condensate-B&R Drawing No. 2006 Feedwater Heater Drains-B&R Drawing No. 20C ' Secondary Services Closed Cooling Water-B&R Drawing No. 2018 Circulating Water & River Water Chemical Treatment-B&R Drawing No. 2021 Circulating & Secondary Services Water-B&R Drawing No. 2023 Reactor Coolant Makeup & Purification-B&R Drawing No. 2024 Intermediate Closed Cooling Water-8&R Drawing No. 2029 Nuclear Services Closed Cooling Water-B&R Drawing No. 2030 Sampling Nuclear System-B&R Drawing No. 2031 Nuclear Services River Water-B&R Drawing No. 2033 Reactor Building Ventilation & Purge-8&R Drawing No. 2041 Reactor Building Normal Cocling-B&R Drawing No. 2046 Reactor Coolant Pump Seal Recirculating & Cooling Water-B&R Drawing No. 2601

I 1.2 Operating Procedures Applicable for Operation 1.2.1 2102-3.2, Unit Cooldown 2.0 195 241

b' ',5 2102-3.1 Revision 0 06/20/77 1.2.2 2103-1.9, Reactivity Balance Calculations 1.2.3 2103-1.3, Pressurizer Operation 1.2.4 2104-1.2, Makeup and Purification System 1.2.5 2105-1.4, Integrated Control 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 21'6-1.1, Main Steam 1.2.10 2iO6-2.4, Feed System 1.2.11 2106-1.2, Extraction Steam, Stage Heater Vents & Drains 1.2.12 2104-3.6, Circulating Water 1.2.13 2104-1.6, Intermediate Cooling System 1.2.14 2106-2.1, Condensate System 1.2.15 2103-1.5, Hydrogen Addition and Degasification 1.3 Manufacturer Instruction Manuals 1.3.1 Diamond Pcwer " Control Rod Drive Mechanism Control System" instruction manual Volume I a.nd II 01-0115-02 and 01-0116-01. 1.3.2 Sailey "eter Company " Integrated Control and Non-Nuclear Instrumentation System" instruction manual Volume I A, Volume 1B and Volume 2. 1.3.3 Babcock & Wilcox, " Physics Test Manual," TMI-2. TG 06-000-23. 1.3.4 Westinghouse, " Steam Turbine for Jersey Central Pcwer & Light Unit 2" Instruction Scok Volume I (I 3. No. 1250-C734). 1.3.5 Westinghouse " Hydro Inner Ccoled Turbine Generator for Jersey Central Power & Light Unit 2" Instruction Book (I.S. No. 20742). 3.0 195 242

2102-3.1 _. p.- j Revision 4 04/18/78 + l.4 Applicable System Descriptions 1.4.1 Not Applicable 1.5 Curves, Figures, Tables, etc. 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 8 - Minimum Boric Acid Tank Contained Volume / Concentration. Figure 9A - Core Power Vs Rod Position Bands 4 Pump Operation (0-200 EFPD) ~ Figure 9B - Core Power Vs Rod Posititn Bands 3 Pump Operation (0-200 EFPD) ~ Figure-9C - Core Power Vs Rod Position Bands 2 Pump Operation (1-200 EFPD) Figure 10 - Bcrate/Deborate + 10% Rod Position.(60L-140 EFPD). Figure 11 - RC Boron Change Needed to Reposition Rods in Bands. l Figure 12 - Ainimum Feed and Bleed Flow Rate per Load Change

• s. RCS Boron Concentration.

195 243 4.0

2102-3.1 f d Revision 4 04/18f78 Figure 13 - Pressurizer Level vs. T-ave. Figure 14 - Shutdown Boron Concentration vs. EFPD. 2.0 LIMITS AND PRECAUTIONS l 2.1 Equipment l 2.1.1 Maintain gland sealing after turbine is taken off line. i i 9 195 244 1.1

kevision7 12/2 Maintain pressurizer level within the limits of Figure 13. 3/78 2.1. 2 2.1. 3 The pressurizer spray valve minimum bypass flow must be maintained 2 1 gpm. 2.1,4 Do not feed stear, generators via auxiliary feed nozzles except during emergency conditions or unless feedwater temperature is within 50 F of both RC System and 0TSG shell', however, the auxiliary feed nozzles must be used for filling an e.npty OTSG (< 10 inches startup level) when RC temperature is above 200 F. 2.1.5 For normal plant heatup and cooldown conditions the maximum delta T between the feedwater line temperature and steam generator lower downcomer temperature is 440 F when using the main feedwater nozzles. 2.1. 6 When operating letdown coolers, intermediate cooling pumps and intermediate coolers must be in operation. 2.1. 7 When turbine load is less than 75 MWE (15% reactor power) verify that the turbine bypass valves operate to maintain header pressure setpoint. 2.1.8 Maximum allowable OTSG fill rate is 500 gpm per steam generator. 2.1. 9 Maximum allowable.sT between RCS and OTSG average shell temperature is 60 F. ~ 2.1.10 During startup and shutdown, when Groups 1&2 are withdrawn, OTSG water level shall be mat tained between 97.tnd 99 percent on operating level instrumentation. If OTSG water level exceeds 390" (i.e. > 100% in the operate range), invoke action statement b of T.S. 3.4.5. I 195 245 5.0

.e 2102-3.1 Revision 0 06/20/77 2.1.11 Maintain Makeup and Purification System baron concentration equal to or greater than the baron concentration of the RC System durin. the process of reducing power and cooldown of the RC System. 2.1.12 Do not attempt to start a Reactor Coolant Pump when power is greater then 30%. 2.1.13 With a filled and vented RC System, do not fill, drain, c;- blow an OTSG dry without flow in the RC System. Flcw may be through Decay Heat or RC Pumps. Rate of fill, drain, or blowdown ', hall not decrease RC System temperature (T-cold) or U OTSG downcomer temperature by more than 50 F below initial temperature. 2.1.14 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 folicwing equation or the startup will be terminated until an appropriate evaluation is made. SDM1 (100 - SDM2) g _ SDM2 (100 - DSM1) .:here M = Multiplication factor SDM1 = Shutdown Margin Prior to reactivity (.% ak/k). SDM2 = Shutdown Margin after reactivity (% ak/k). t!0TE: SDM1 and SDM2 are negative valves. 2.1.15 When operating from 50 to 100% rated power with 4 RC pumps running, maintain cold leg differential temperatures less than i 5 F. During load transient near rated power maintain cold leg U differential less than 10 F. 6-195 24" ~ = 2.

a .4 2102-3.1 Revision 0 C6/20/77. NOTE: With less than 4 RC pumps running the cold leg temperat, re may exceed these limits but not over 20 F. 2.1.16 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 wors* case Thermal Condition (Group 20) data dump should be taken every EFFD. The reactor power level, boron 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 Summary for delivery to the Station Nuclear Engineer.

2.1.17 Folicwing a significant one-step load change (>10% rated power)_ above 50% rated power or significant control red motion (>10% insertion or withdrawal) a Worst Case Thermal Condition should be taken within one hour after the change and then every 4 to 8 hcurs for a period of 24 to 36 hours, or longer if evidence of a power distribution transient exists. A 3-D Power Map should be taken about 1 hcur af ter reaching steady-

1. _

~ state conditions. These data printouts are not necessary on the way up to full power if the mechanical maneuvering recommendations are followed. However, the data from Goups 20 and 34 should be called out one hour af ter the pcwer hold level is reached. t 2.1.18 Obtain a 3-D pcwer may whenever a large imbalance or any other core flux abnormality exists. 7.0 '195 247

tiO2-3.1 Revision 3 02/13/78 2'.l.19 Maintain all control rods and axial power shaping rods within + 6.5% (indicated position) of their group average height (T.S. 2.1.3.1). 2.1.20 Except for physics tests or exercising control rods, the control rod insertion / withdrawal limits are specified on Figure 3, Figure 4 and Figure 5 of 2102-2.1 for various RC pump combinations. If control r.od position LOCA limits are exceeded, proceed with T.S. Action Statement 3.1.3.7. If control rod position Shutdown Margin Limits are exceeded, proceed with T.S. Action Statement 3.1.1.1. 2.1.21 Conduct surveillance testing as listed on the surveillance test schedule in accordance with Administrative Procedure 1010. Maintain shift logs in accordance with Administrative Procedure 1012. 2.2 Administrative 2.2.1 Sring buraticr. verify boren corce.,tration every estimated 30 pp3-2.2.2 "aintain makeup tank level above the low level alarm. 2.2.3 Ccoldown rate shall be no greater than 100 F/hr. 2.2.4 ^ :aldown of the R.C. System without degassing may result in excessh[drogenandairborneradioactivitywhenreactorcoolant system is cpened to atmosphere. 2.2.5 If any Safety Limit (defined in Technical Specification 2.1 and 2.2) is exceeded, the Shift Supervisor shall notify the Station / Unit Superintendent. The reacter shall be placed in HOT standby within one hour. The licensee shall notify the 195 248 s.0

~ ~..:.... f'__' O , y _. ,,., _ ; _ z..,., _. ,u l - - - m v ,t* d ^ 1 2102-3.1 Revision 0 06/20/77 Commission, review the matter and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude reoccurrence. Operation shall not be resumed until authorized by the Commission. 2.2.6 If, during operation, the automatic safety system does not function as required, the Station / Unit Superintendent shall be notified. The Shift Supervisor shall take appropriate action as outlined in the Tech. Specs. Tne reporting requirements of T.S. 6.9 shall be followed. Note that this appropriate action may include shutting down the reactor. 2.2.7 When a Limiting Condition for Operation (LCO) (. defined in Section 3 of the Technical Specificat'ons) is not met, the shift supervisor shall notify the Starion/ Unit Superintendent. The reactor shall be placed in at least HOT STANDBY within 1 hour and in COLD SHUTDOWN within the folicwing 30 hours unless corrective measures are ccmpleted that permit operation under the permissible ACTION statements for the specified time inter'tal as measured from initial discovery. The reporting requirements of T.S. 6.9 shall be followed. 2.2.8 Quadrant tilt shall be monitored on a minimum frequency of once cvery twelve (.12) hours during power operation above 15% of rated power. The QUADRANT POWER TILT shall not exceed the limits listed in Table 3.2-1 of Tech. Spec. (Tech Spec. 3.2.4). 2.2.9 When reactor power is less than 10% FP, do not request a printout of the following computer grcups: 9.0 '195 249

2102-3.1

l Revision 3

.m 02/13/78 Gp. # 20 Worst Case Thermal Condition 31 Fluid Condition 38 Core Average Thermal t,ondition 39 Core Map Thermal Condition 40 All Thermal Output 53 Selected Assembly Thermal Condition 2.2.10 AXIAL POWER IMBALANCE shall be maintained within the limits shown on Figures 3.2-1, 3.2-2 and 3.2-3 of Tech Spec (TS 3.2.1) when above 40 percent of the Rated Thermal Power except for Physics Test (TS 3.2.1). 2.2.11 The reactor control rod position and boron concentration shall be maintained such that an available shutdown margin of at least ((> 2% ar./K when Keff > 1.0) exists with the single 1", aK/K when Keff 71.0) most reactive rod stuck cut (TS.3.1.1.1. ) .2.12 On annunciation of an Asyrcetric Fault on Control Rod Drive, verify the status of the rods in the group. All control rods should be cperable and positioned within 9 inches (+ 6.5% ~ indicatec position) 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. 2.2.13 AXIAL POWER I,"SALANCE shall be maintained within the limits shown on Figures 3. 2-1, 3.2-2 and 3.2-3 of Tech Spec 3.2.1 (Figure 2 attached). The AXIAL POWER IMBALANCE shall be .?. determined to be within limits at least once every 12 hours when above 40% of RATED TEP"AL F0WER except uhen an AXIAL r POWER IMBALANCE (ccmputer alarm packaga) monitor is inoperable, 10.0

2102-3.1 Revision 3 then calculate the AXIAL POWER IMBALANCE at least once pep 3/78 0 hour. 2.2.14 If axial power imbalance exceeds the limits specified, restore the axial imbalance within limits in 15 ' minutes or be in HOT STANDBY condition within 2 hours. 2.2.15 The Regulating Rod groups shall be limited in physical insertion as shown on Figures 3.1-2, 3.1-4, and 3.1-6, 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 limits proceed with T.S. Action Statement 3.1.3.7. With the regulating rod group inserted beyond the Shutdown Margin limit proceed with T.S. Action Statement 3.1.1.1. 2.2.16 The approval of the Shift Supervisor, Radiation Protection Supervist, and Unit / Station Superintendent, must be obtained if maintenance or extendej 'nspections must be performed within P e secondary shield. in top of the "D" Rings, or in the reactor head a. a '.. hen the reactor power is greater than 15. Reacter pcwer must not be increased until such work is completed or the situation is re-evaluated and further approval is cbtained from the Radiation Protection Supervisor, Shift Supervisor, and Unit / Station Superintendent. 2.2.17 Follo. wing a Refueling Period, Startup, or similar operational occurrence which could altei the mixture of radionuclides in the reactor coolant, an analysis for individual gamma emitters [ should be performed at the condenser vacuum pump discharge. 2.2.18 Power operation with at least one idle reactor coolant pump or one idle RC pump in each loop is restricted to 4 hours without having changed the RPS Setpoints. If the reactor s not 95 251 11.0

2102-3.1 Revision 0 06/20/77 returned to an acceptable RC pump operati1g combination at the end of the 4 hour period, the reactor may be operated at restricted powar level defined in Tech Spec 3.4.1. 3.0 IllITIAL CONDITIONS Indicate satisfactory completion by initialing each step. 3.1 Unit is at power. 0 3.2 Unit Tave is being controlled at 582 F and Reactor Coolant pressure is at 1 2155 psig. 3.3 Two main feedwater pumps, two condensate pumps and condensate booster pumps are operating, if power is greater than 40 percent of RTP. _3. 4 Circulating Wa'er System in operation per 2104-3.6. 3.5 Auxiliary Steam is available. 3.6 RCS shutdown Baron concentration for various first cycle temperature ranges have been determined and are shown in Figure 14. Soron concentration in excess of the applicable baron concentration in Figure 14, will ensure >T percent ak/k S.D. margin, is available. 3.7 Pressurizer level control in " Auto" and controlling at the set point in accordance with Fig. 13. 3.8 Verify that make up water at the required baron concentration is available to be added to the Make Up Tank when required as per 2103-1.2. 4.0 PROCEDURE 4.1 Normal Unit Shutdown NOTE: Indicate scsfactory ccmpletion of belcw steps by initialing each step and sign name at end of applicable section. I95 29 12.0

6, .I e 2102-3.1 Revision 0 06/20/77 4.1.1 If tne RCS is to be cooled dcwn, RCS degassification is in progress per 2103-1.5. 4.1.2 From plant computer demand performance data output and log the following in the Control Rocm Operator's Log Book: a) Date and Time b) Reactivity Balance from the computer (Operators Group 22) c) Rod Position d) Boron Concentration e) Reactor Coolant f.verage Temperature f) Effectiva Full Power Days (EFPD) g) Notify Unit 1 of Shutdown. NOTE: Folicwing any thermal power change of more than 15% of rated thermal power within a one (1) hour period, notify HP/ Chem that primary coolant must be sampled and analyzed for Icdine (including I-131, I-133 cnd I-135) between 2 and 6 hours following the change per 2304-SA4. This isotopic analysis of the primary coolant shall continue at 4 hour intervals until the specific activity drops below 1.0 pCi/gm dose equivalent I-131 or 100/E pCi/gm. (T.S. 4.4.8). CAUTION 1: 'Jhile reducing load do not exceed a load ) a reduction rate of 2% per minute until 40% load. 13.0 253

r.u. w w a u / CAUTION 2: Maintain control rods in the transient rod position band (Figure 9) per 2102-2.1. 4.1.3 Notify the load dispatcher and with his concurrence reduce unit load to approximately 40%, by establishing unit load demand of 38.4% at the Unit Master. CAUTION: If load is to be held at less than 50% power for longer than 48 hours, remove the second stage MSR tube bundle from service by closing MS-V31A/B, MS-V32 A/B, MS-V36A/B, and MS-V37A/B. 4.1.4 At approximately 384 MWE (40% reactor power), when the required Feed Water flow is within the capability of one Feed Water pump place one Feed Pump Turbine in Hand by the following procedure: NOTE: Either Feed Pump Turbine may be placed in Hand. a. Place the MV-Pos switch to "MV" and read the difference between Auto and Manual demand. It should read 50% (zero error). If not, use the Bailey Raise-Lower switch and adjust the manual demand until the error is zero. b. Place the selected Feed Pump Turbine Bailey H/A Station to Hand by depressing the Hand pushbutton until the " Hand" light is lit. c. Using the Raise-Lower switch on the Feed Pump Turbine Bailey H/A Station that has been placed in Hand, decrease the speed of the " Hand" Feed Pump to mininum and check that the Auto Feed Pump Turbine is assuming ) the Feed Water Load. (The speed of the Feed Pump Turbine on " Hand" should decrease and the speed of the Feed Pump Turbine on " Auto" should increase). 14.0 e -.m.

2102-3.1 a Revision 4 04/18/78 d. Reduce the speed of Feed Pump Turbine on " Hand" to inimum with the SU/ Load Limit Switch and shut the Feed Pump Turbine down as per 2106-2.4. 4.1.5 Stop one of the operating Heater Drain Pumps in accordance with 2106-1.2, thereby leaving one Heater Drain Pump operating and another in Standby Mode. NOTE: Monitor moisture separator-reheater drain tanks, feedwater heaters, and the heater drain tank to ensure proper water levels are being maintained. 4.1.6 At ; 40% unit load, open the deaerating steam valves EX-V71A and EX-V718. CAUTION 1: While reducing load below 40% load (384 MWE) do not exceed a load reduction rate of 1/2 per cent per minute. CAUTION 2: Maintain control rods in the transient rod position band (Figure 9A, 98, or 9C) per 2102-2.1 4.1.7 Reduce unit load to approximately 35% by establishing the Unit load Demand of 33.6% on the !! nit Master. 4.1.8 Af ter the load is stablized at 35% RTP, place the Feed Pump ~ Turbine Speed Change-the for operating Feed Pump in " Hand" as follows: a. Place the MV-Pos switch to "MV" and read the dif ference 3 between Auto and Manual demand. It should read 50% (zero { error). If not, use the Raise-Lower switch and adjust the manual demand until the error is zero. 'l95 255 15.0

21u2-3.1 Revision 4 04/18/78 Place the selected Feed Pump Turbine speed changer to b. Hand by depressing the Hand pushbutton until the Hand" light is lit. CAUTION: Ensure Feedwater Control Valve AP is maintained at 2,35 PSID. c. Lower Feed Pump Turbine speed using Bailey H/A Station to 3000 RPM. d. Continue to lower Feed Pump speed using the Feed Pump turbine SU/ Load Lhiit Switch as necessary to maintain 3, 35 PSID across Feedwater Control valves. 4.1.9 Reduce power to 20%, by establisn:ng the Unit Load Demand at approximately 19.2%. NOTE 1: Do not exceed the power reduction rate of 1/2 percent per minute. (Rate applicable below 40% power). NOTE 2: Maintain Control Rods in the Transient Rod Position Band (Figure 9A, 9B, or 9C) per 2102-2.1. 4.1.10 When plant load has de;reased to 205, stop all heater drain pumps by placing their Panel 5 control switches in ~ -PULL-TO-LOCK. 4.1.11 Verify MS-FHS-4374 at Panel 17 is in Auto and when the load has decreased to about 20%, ascertain from Panel 17, that the turbine drain valves, MS-V281 A and B, MS-V283, MS-V284, and MS-V286 A and B, have opened. If not, use I MS-FHS-4374 Panel 17 to attempt to open then. 4.1.12 a. Place the condensate / condensate bocuter pump set selector switch to manual en Panel 5. 16.'0 195 256

2102-3.1 Revision 4 04/.8/76 b. Stop one condensate booster pump by placing control switch to stop position on Panel 5. c. Stop one condensate pump by placing control switch to stop position on Panel 5. d. Place condensate /condensa'e booster pump set selector switch to.Suto. 4.1.13 Commence increasing RC System Boron concentration to the value determined in "ection 3.6. NOTE 1: Do not exceed the power reduction rate of 1/2 per cent per minute. (Rate applicable below 40% RP). NOTE 2: Maintain the control rods in the transient rod position band (Figure 1A, 98, or 9C) per 2102-2.1. 4.1.14 Reduce power to 15% by establishing the Unit Load Demand to 14.4%. 4.1.15 Place the SG/Rx Demand H/A station in Hand and decrease SG/Rx demand to ;:ero by the following procedure: a. Place the MV-Pos switch to "Pos" and place the SG/Rx Master in Hand by depressing the Hand pushbutton =:. until the " Hand" light is l'it. The "SG/Rx !! aster on I'Idnual" alarm Will sound. [CS is f.ow in track. b. Using the Raise-Lower switch, decrease SG/Rx demand to zero. [ NOTE: If OTSG low level limit was not reached during 4.1.14, some power reduction may be associated with this step. '25 257 17.0

ciU2-3.1 Revision 5 07/07/78 4.1.16 Before either Steam Generator goes on low level limit, place the Steam Generator load Ratio ATc H/A station in Hand by the following procedure: NOTE: If either Steam Generartor is on los level limit, go to step 4.1.16.b. a. Place the MV-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). b. Place the Steam Generator Load Ratio ATc H/A station to Hand by depressing the Hand pushbutton until the " Hand" light is lit. c. Use the Raise-Lower switch and adjust ATc demand to zero as read in "Pos." 4.1.17 Resume Feedwater heating by Aux steam and secure Feedwater heating by extraction steam in accordance with 2106-1.2. 4.1.18 Depress the "0PER AUT0" pushbutton. The "0PER ICS" pushbutton lamp will go off, and the "0PER AUT0" lamp should come on. Verify main turbine on manual alarm annunciates. 4.1.19 Reduce the Turbine Load to approximately 50 MWE as follows: a. With the Turbine in "0PER AUTO," set the setter to 50MW - by pressing lower butian. b. Set the load rate per 2106-3.1 (later) MW per minute. c. Press IMP OUT button. d. Press "G0" button. 2 NOTE: For operation at or below 10% load for more than 15 i minutes, the :nd stage reheater rantrol valve should be positioned to maintain the LP Steam inlet temperature to 400F. Depress the "400F" pushbutton on the MRS controller, panel 16. l05 258 18.0

Revision ~5' '4.1.20 Observe the Turbine Bypass valves (MS-V25A, MS-V25B, MS-V26A, and MS-V268) open gradually as Turbine Genarator load is ~ reduced. Verify that Turbine Bypass VMyes maintain the Turbine header pressure between 895 (2nd 885 PSIG. 4.1.?1 Start the AC Turning Gear Oil Pump, and the Seal Oil Backup Pump (TGP-SOP) from panel 5. 4.1.22 Place the bearing lift pump (BL) control switch on Panel 5 to AUTO. The BL pump should start when the turbine speed decreases below 500 RPM. 4.1.23 Insure the DC Emergency oil pump (EOP) is in the fiormal-After-Stop position, and the turning gear control switch is in " Auto". 4.1.24 When load has decreased to approximately 50 MWE notify the Load Dispatcher and with his concurrence trip the Turbine by depressing the Panel 5 Trip pushbutton. 4.1.24.1 Insure turbine throttle valves, governor valves, reheat stop valves, and interceptor valves fully close. 4.1.25 Verify the generator breakers 82-02 and 82-2602 have opened, or open them manually by: a. Verify turbine inlet valves are all closed. L'. Depress the Trip select for B2-02 (B2-2602). c._ VERIFY that the Green backlight and the Yellow Point Selected lights are lit. d. PLACE the control switch for B2-02 (B2-2602) to trip and release. e. Verify Green trip indication for the breaker. f f. TRIP the other Generator Breaker as per steps a thru d above. g. If the unit is not going to resynchronize within one hour, align the 500 KV substation for generator shutdown 95 259 ~ per 2107-1.3, section 4.6.1. 19.0

2102-3.1 '} 9evision 6 09/22/78 4.1.26 Trip the Field Breaker. I'OTE-When the field breaker is tripped the Regulator is shut off, the base adjuster is positioned to the no load preposition point and the ground detection system is shutdown. 4.1.26.1 Reduce the number of operating CW pumps to a maximum of 4 pumps. l 4.1.27 Ensure all Turbine Extraction Steam Erain Valves are opened. 4.1.28 Place the Voltage Regulator / Cutoff Switch in the OFF position to match indicate status. 4.1.28.1 It is important to manually regulate cooling water to the hydrogen U seal oil coolers to maintain the oil temperature between 95 F U and 110 F. Colder 'il may damage the H seal rings, and 2 result in a hydrogen leak. d.1.29 Regulate water to the oil coolers, by the controller on panel 5, to maintain an oil temperature leaving the coolers, between 95 and 100F. NOTE: Turbine should take 3 75 minutes to slowdown to turning gear engage speed. 4.1.30 Irsure turning gear operation per 2106-3.2. 4.1.31 The cacling water to the generator coolers may be shut of-when the hot gas temperature (pt 13 YM-TR-1926) is less than U 95 F: 4.1.32 At the Reactor Demand H/A station, place the MV-Pos switch to "Pos" and read the Reactor demand. It shculd be the same as neutron power as indicated on Panel 4. P;c.ce the Reactor .[ Cemar.d H/A station in Hand by depressing the Hand pushbutton until the " Hand" light is 7. it. 20.0

diO2-3.1 Revision 6 09/22/78 CAUTION: DECREASE REACTOR DEMAND AT A RATE WHICH DOES f;0T U EXCEED A MAXIMUM C00LDOWN RATE OF 100 F/hr. 4.1.33 Verify the Reactor demand MV-Pos switch is in "Pos" reading Manual Reactor demand. Use the Raise-Lower switch decrease Reactor Demand to 10%. 4.1.34 Close Letdown Isolation Valve MUV-376 and add water to MU tank per 2104-1.2 as required. 4.1.35 At 10% power, place the Loop A & B Feed Water demand H/A stations in Hand by the following procedure: a. Place the MV-Pos switch to "Pos" both stations should read 0%, if not, balance Feed Water demand stations at 0% demand. b. Place the Feed Water demand "A" H/A stations in Hand by depressing the Hand pushbutton until the " Hand" light is lit. c. Using the Raise-Lower switch insure Feed Water demand A is at 0%. d. Repeat steps b & c above for Feed Water demand "B" station. 4.1.36 Place the main Feed Water valve H/A stations in Hand by the following procedure: a. - Place the MV-Pos switch to "Pos" and verify Auto demand is 0%. b. Place the Main Feed Water valve in Hand by depressing the Hand pushbutton until the " Hand" light is lit. Check { "Pos" indication to insure manual demand is zero. 4.1,37 Place the Start-up Feed Water valves to " Hand" by the following procedure: 195 261 I 21.0

Revision 7 Place the MV-Pos switch to "Pos" and note Auto dedar[c[.3/78 2 a. b. Place the Start-up Feed Water valve in Hand by depressing the Hand pushbutton until the " Hand" light is lit. Check "Pos" indication to insure manual demand is opproximately what it was in Auto. c. Mode 1 to Mode 2 checklist (Appendix A) should be completed before proceeding with next step. CAUTION 1: Maintain Tave within limits of 2101-1.1, Figure 1.0-07.1. o U CAUTION 2: Do not exceed cooldown rate of 100 F per hour. 4.1.38 Maintain the 0TSG level.s at the LLL and lower power to 5%. CAUTION 1: Maintain Tave within limits of 2101-1.1 Figure 1.0-07.1. CAUTION 2: If Tave drops below 530 F complete SP2311-2 (TS 3.1.1. 4 ) CAUTION 3: If

turn to power is anticipated place the pressurizer level controller to manual and maintain the pressurizer level within the limits of Figure 13.

Finally reducing the level to 100 inches. (25%) CAUTION 4: Establish flow through the OTSG dri.in cooler per 2106-2.5 and open FW-V66A/B to maintain level at the LLL. 4.1.39 At 5 percent reactor power, place the Diamond Rod Control -s -8 Station to manual and gradually reduce reactor power to 10 amps on the Intermediate Range instrumentation. 4.1.40 When the reactor is stable at 10-8 amps with zero startup rate, record critical data in the Control Room Logbook: boron 195 262 22.0

Revision 7 12/23/78 ppm, RCS temperature, rod position, and time /date. Mode 2 to 3 (Apperdix B) c W klist should be completed before proceeding with the next step. 4.1.41 Insert regulating groups 7/6 & Sand 4 and 3 to In-Limit and leave group 8 at previous operating position. 4.1.42 With the Reactor Coolant Average Temperature between 532 and 525 F, the Safety Rod Groups (1-2) withdrawn, and the reactor greater than 1 percent shutdown the plant is in llot Standby condition (Mode 3). NOTE: If unit is in Hot Standby greater than 24 hours, U verify baron is greater than Tav WO F curve on Figure 14 prior to flooding nozzles. 4.1.42.a Place the SU FW RV's in " Hand" and maintain OTSG levels between 97 and 99% on the Operating Range. Ensure boron concentration 0 is greater than Figure 14 curve "Tave <300 F". If water level exceeds 390" (i.e. > 1005 in the operate range) invoke action statement b of Tech Spec Paragraph 3.4.5. 4.1.43 If cocidown is intended, reduce the number of operating RC Pumps to one pump per loop in accordance with 2103-1.4. Maintain RCS pressure / temperature within the single pur-in a loop operation curve. 4.1.44 Open the Generator Disconnect Switches as directed by Load Dispatcher per 2107-1.3. 4.1.45' Complete the Reactor Building inspection, if required. ~3 23.0 195 263

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g 2102-3.1 Revision 1 08/04/77 110 100 I gg (-C. 3,92) 6' (16.6,92) (-16. 7,32 ) (19.2,80) = 70 E R 60 PERMISSIBLE RESTRICTED o 50 OPERATING REGION h ( -2 8'.1. 4 3) fiEGION s' 40 25.4,40) 4 20 10 0 -50 -40 -30 -20 -10 0 10 20 30 F 50 !=calance (".) CORE IL'2ALANCE VS F0YER LEVEL (0 200 i 10 EFPD'S) Fi gu re J. 2-3 195 265 as.o

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R t 2102-3.1 Revision 4 / VS* 04/18/78 L0tlG-TERM OPERATIt'G Arid TRAtlSIEflT R0D POSITIO 1 BAtl]S X TMI 2 CYCLE 1 (0-200 10 EFPD's) 3 PuliP OPERATI0tt FIGURE 98 d '. 1.2 j.... ~ LLI.._...:,. ._I i._... _ 1 1... - 4 _ 'l. ._.)__ 4.. Long-Tera Operating Rod Position Band r ; 7g [..?,_ [ _ _ _ p,... _ h _. [. <. s...]......[.?__e ,r e g ..w., Trnasient Rod Position Band _ _.L, ,.-_. 4 _. y___. _ i .e. _. i y _..L -.4__ . _ +. I. n _.. _._100. a ___ __n ...,p . '4_. .-.] . I-t_ =. L. 90 c'f -_. _. c-w s ..,Or. .__ u . x,. l g .- 80 g..._.. - j. 3

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