ML20096B431
| ML20096B431 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/31/1995 |
| From: | Rainey G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CCN-96-14005, NUDOCS 9601160259 | |
| Download: ML20096B431 (58) | |
Text
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Delta. PA 17314-9739 717 456 7014 January 11,1995 CCN 96 14005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Mail Station P1-137 Washington, DC 20555
Subject:
Peach Bottom Atomic Power Station Unit No. 3 Report of Plant Startup Following The Tenth Refueling Outage Gentlemen:
Enclosed is the Peach Bottom Atomic Power Station Startup Report for Unit No. 3 Cycle 11. The report is submitted pursuant to reporting requirement 6.9.1.a in Appendix A to Facility Operating License No. DPR-56.
Sincerely, ra . Rainey Vice President,
)
Peach Bottom Atomic Power Station i
GRR/RBW '
Enclosure cc: ..) B.W. Gorman, Public Service Electric & Gas
, R.R. Janati, Commomwealth of Pennsylvania W.L. Schmidt, USNRC Senior Resident Inspector, PBAPS R.I. McLean, State of Maryland T.T. Martin, Administrator, Region 1, USNRC H.C. Schwemm, Atlantic Electric A.F. Kirby, Ill, Delmarva Power INPO Records Center !
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v PECO ENERGY PEACH BOTTOM ATOMIC POWER STATION CYCLE 11 STARTUP REPORT UNIT 3 SUBMITTED TO THE U.S. NUCLEAR REGULATORY COMMISSION PURSUANT TO FACILITY OPERATING LICENSE DPR-56 DECEMBER 1995
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TABLE OF CONTENTS Executive Summary 1 1.0 Purpose . 2 2.0 Program Description 2 j 3.0 Acceptance Criteria 4 4.0 Rerate Startup Test Program Summary 4 :
5.0 Chronology of Events 6 6.0' Test Results Summaries l
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STI-1 Chemical & Radiochemical 13 STI-2 Radiation Measurements 15 STI-4 Shutdown Margin 18-STI-5A CRD Insert / Withdraw Times 19 STI-5B CRD Scram Timing 20 STI-11 LPRM Calibration 22 STI-12 APRM Calibration 23 STI-14 RCIC 24 STI-15 HPCI 27 STI-18 Core Power Distribution 30 STI-19 Core Performance 31 STI-22 Pressure Regulator 33 STI-23A Feedwater Level Control 39 STI-25 Main Steam Isolation Valvec 41 STI-33 Turbine Stop Valve ST 43 STI-34 Turbine Control Valve ST 46 STI-35 Recirc. System Flow Calibration 49 STI-72 Drywell Atmospheric Cooling 50 STI-80 Thermal Performance Test 51 STI-81 I&C Surveillance Tests 52 STI-82 Steady State Data Collection 53 TABLES and FIGURES TABLE 1 - Tests Performed for Power Rerate 10 FIGURE 1 - Rerate Power / Flow Map 11 FIGURE 2 - RCIC Acceptance Curves 12
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,e , Peach Bottom Atomic Power Station l Unit 3 Rerate Startup Test Report Page 1 of 55 EXECUTIVE
SUMMARY
This Startup Test Report is submitted to the Nuclear Regulatory l Commission (NRC) in accordance with the requirements of Peach Bottom Atomic Power Station (PBAPS) Technical Specification 6.9.1.a. The report summarizes the startup testing performed on PBAPS Unit 3 following the implementation of Power Rerate during ,
the Fall 1995 Refueling Outage. I The result of Power Rerate is an increase in reactor power equal to 5% of the original rated thermal power. All testing identified within the PBAPS Updated Final Safety Analysis Report (UFSAR)
Chapter 13.5 was addressed and evaluated for applicability to this increased licensed power rating as required by Technical Specifications.
The 18 day program began when the Reactor Mode Switch was placed in the Startup position on October 15, 1995. The unit was synchronized to the grid on October 17*, marking the official end to the Unit 3 10* refueling outage. The new rerated 100% power (3458 MWt) was first achieved on October 22, 1995. All required Rerate Startup Tests were completed by November 1, 1995.
Over 66 Rerate Startup Tests were performed satisfactorily during the startup. No programmatic Level 1 or Level 2 failures occurred.
A total of two (2) Test Exception Reports (TERs) were initiated during the testing program for reasons other than program failures. ,
TERs document unexpected or unsatisfactory conditions encountered during' testing. All Test Exceptions were satisfactorily dispositioned. No further actions resulting from the TERs are required.
No adjustments were required to control systems for the following plant systems: EHC - Pressure Regulator, Feedwater, Recirculation, or Reactor Core Isolation Cooling (RCIC). Minor adjustments were made to the High Pressure Coolant Injection System (HPCI) control system. All systems performed in a stable manner during the plant startup and during transient testing. The unit is operating very well at rerated conditions.
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,, , Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 2 of 55. ,
1.0 Purpose This Startup Test Report summarizes the testing performed on Peach Bottom Atomic Power Station (PBAPS) Unit 3 following the implementation of Power Rerate. The result of Power Rerate is an increase in reactor power equal to 5% of the original rated thermal power. All testing identified within the PBAPS Updated Final Safety Analysis Report (UFSAR) Chapter 13.5 was l addressed and evaluated for applicability to this increased licensed power rating as required by Technical Specification 6.9.1.a. The Rerate Startup Test Program Plan documents these evaluations and describes in detail the testing performed for power rerate. Each test performed for power rerate is described herein, including the test purpose, description, acceptance criteria and results. This report is submitted in accordance with the requirements of Technical Specification 6.9.1.a.
2.0 Program Description l
The power rerate startup testing requirements were developed I primarily from the review of Chapter 13.5 of the PBAPS UFSAR, ;
Section 10.3 of the GE Power Rerate Safety Analysis Report for Peach Bottom 2 & 3, and the GE Power Rerate Project Rerate Confirmation Test Program. The results of this testing determined the unit's ability to operate at the rerated power l level. The testing was conducted following the loth 7ggggling l outage for Unit 3.
The majority of testing can be summarized into the following categories:
- 1) Verifying control systems (Feedwater, EHC - Pressure Regulator, and Recirculation) are stable at rerate conditions.
- 2) Verifying high pressure injection systems (Reactor Core Isolation Cooling, High Pressure Coolant Injection) operate acceptably at rerated pressures.
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- 3) Data collection for comparison to original plant rated conditions and for use as a baseline for rerate conditions (Radiation surveys, Chemistry, Thermal Performance, Balance of Plant Steady State Data).
,, , Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 3 of 55 2.0 Program Description (Continued)
Test Conditions at which the testing was performed are defined below. All testing within a Test Condition must be completed prior to proceeding to the subsequent Test Condition. Reactor core flow can be any flow within the safe operating region of the power / flow map (Figure 1) that will produce the required power level.
Rerate Test Condition Power Level' Rerate MWT 1 <85% <2939 2 85%-86% 2939 - 2974 3 90%-91% 3112 - 3147 4 95%-96% 3285 - 3320 5 97%-98% 3354 - 3389 6 99%-100% 3423 - 3458 All testing within a Test Plateau must be completed and approved by the Rerate Startup Test Director and the Reactor Engineering Branch Head prior to increasing power to the subsequent Test Plateau. If a Level 1 failure occurs during testing; resolution and approval to increase power to the subsequent Test Plateau must be approved by PORC (Plant Operating Review Committee). No Level 1 failures occurred.
Rerate Startup Test Plateaus are defined below.
Test Plateau A (s91%) -
Includes testing at Test Conditions 1, 2, & 3. Reactor thermal power cannot exceed 91%.
Test Plateau B (s96%) -
Includes Test Condition 4 testing. Reactor thermal power cannot exceed 96%.
Test Plateau C (s98%) -
Includes Test Condition 5 testing. Reactor thermal power cannot exceed 98%.
Test Plateau D (s100%) - Includes Test Condition 6 testing. Reactor thermal power cannot exceed 100%.
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,, , Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 4 of 55 3.0 Acceptance Criteria Level 1 acceptance criteria normally relates to the value of a process variable assigned in the design of the plant, component systems or associated equipment. If a Level 1 criterion is not satisfied, the plant will be placed in a suitable hold condition, until resolution is obtained. Tests compatible with this hold condition may be continued. i Following resolution, applicable tests must be repeated to I verify that the requirements of the Level 1 criterion are now satisfied.
Level 2 criterion is associated with expectations relating to the performance of systems. If a Level 2 criterion is not i satisfied, operating and testing plans would not necessarily j be altered. Investigation of the measurements and the l analytical techniques used for the predictions would be started.
Any acceptance criteria failure must be documented on a Test Exception Report (TER).
4.0 Rerate Startup Test Program Summary The test program began when the Mode Switch was placed in Startup on October 15, 1995-and ended with all required Rerate Startup Tests complete on November 1, 1995. The unit was synchronized to the grid on October 17'", marking the official end to the Unit 3 loth refueling outage. The new rerated 100%
power (3458 MWt) was first achieved on October 22, 1995.
In general, the unit operates very well at the rerated conditions. No adjustments were required to control systems for the following: EHC - Pressure Regulator, Feedwater, Recirculation, or Reactor Core Isolation Cooling (RCIC).
Minor adjustments were made to the High Pressure Coolant Injection System (HPCI). All systems performed in a stable manner.
RCIC and HPCI achieved their respective rated flows and pressures well within the design time requirements at rerated pressure conditions. Minor adjustments were made to the HPCI speed control system while performing the HPCI Flow Control stability Test at 100% power. Due to these adjustments, it I was decided to rerun the HPCI Cold Quick Start test. HPCI l again achieved rated flow and pressure well within the design time requirement of 30 seconds during the second run.
Data collected at rerated conditions showed that the 5%
increase in reactor power has little, if any, effect on :
reactor water chemistry and radiological conditions throughout the plant.
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,, , Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 5 of 55 4.0 Rorate Startup Test Program Summary (Continued)
All Rerate Startup Tests were performed satisfactorily during !
the startup from 3R10 refueling outage. Table 1 identifies 1 all of the required Rerate Startup Tests and the Test Conditions in which each test was performed. No Level 1 or Level 2 failures occurred during the program. A total of two (2) Test Exception Reports (TERs) were initiated during the testing program for reasons other than program failure criteria. Brief descriptions of the two TERs are described l below. l I
- 1. The SI for the RPS Card File Functional was not i documented as completed during the outage. It was i completed in normal frequency prior to the outage and 1 changed from a monthly to a quarterly frequency. It was )
therefore not required to be performed during the outage. No changes to the card file were required by ,
power rerate. All changes due to rerate for RPS were '
l performed by instrument calibrations. All instrument calibration procedures were revised and performed.
- 2. While performing the RCIC Quick Start procedure at 950 psig, the process computer could not produce a Core Power and Flow Log via 3D Monicore. It was realized at this point that the 3D Monicore System did not have accurate data to produce the log at this low power level. Alternate indication was used to determine and document Reactor power level. There was no effect on test performance due to this change. All tests at this power level used the alternate indication for power level.
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Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 6 of 55 5.0 Chronology of Events Event Date/ Time Mode Switch to Startup (Test Condition 1) Oct 15/1445 Shutdown Margin Demonstration - Cycle 11 Oct 15/2159 Feedwater Heater Level Controller Adjustments Oct 16/0259 RCIC Operability (not a rerate test) Oct 16/0359 i
Turbine Shell/ Chest Warming Oct 16/1559 HPCI Operability Oct 16/0559 Raise EHC Pressure Set to 940 Psig Oct 16/1359 Drywell Inspection Oct 16/1459 Pull Control Rods until 4 BPV's Open Oct 16/1559 Roll Main Turbine Oct 17/0159 SP-2067 RCIC Quick Start & Stability Oct 17/0259 Synchronize to Generator Oct 17/0159 Increased Power to 20% Oct 17/0259 i
SP-2071 HPCI Quick Start & Stability Oct 17/0759 Increased Power to 25% Oct 17/0359 SP-2084 Pressure Regulator Incremental Oct 17/0436 Regulation SP-2075 Pressure Regulator Stability Oct 17/0959 Rod Block Monitor Cal /Functionals Oct 18/0459 SP-2080 Rerate I&C Surveillance Testing Oct 18/0559 Control Rod Drive Scram Time Testing Oct 19/2059 (approximately 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />)
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,, , Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 7 of 55 5.0 Chronology of Events (Continued)
Event Date/ Time Increased Power to 29% Oct 19/0759 APRM Calibration Oct 19/1159 Recirc Pump 45% speed in-place cal Oct 19/1459 Increased Power to 60% Oct 19/2359 Perform OD-1 (TIP wiring and computer Oct 21/0059 interface delay of 23 hrs & 43 min.)
Increased Power to 75% Oct 21/0259 SP-2073 MSIV Individual Closures Oct 21/0359 CH-420 SJAE Off-Gas Sampling Oct 21/0359 Increased Power to 85% (Test Condition 2) Oct 21/1359 SP-2082 Steady State Data Collection Oct 21/1459 APRM Calibration Oct 21/1459 Increased Power to 90% (Test Condition 3) Oct 21/1559 HP-C-200 Radiation Measurements Oct 21/1759 SP-2079 Thermal Limits Evaluation Oct 21/1759 APRM Calibration Oct 21/1759 SP-2082 Steady State Data Collection Oct 21/1959 SP-2077 Control Valve Surveillance Test Oct 21/2259 SP-2076 Stop Valve Surveillance Test Oct 21/2259 Test Plateau A Results Approved Oct 21/2259 Increased Power to 95% (Test Condition 4) Oct 21/2359 HP-C-200 Radiation Measurements Oct 22/0159 Drywell Temperature Monitoring Test Oct 22/0059 SP-2078 Thermal Performance Data Oct 22/0359
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,, , Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 8 of'55 5.0 Chronology of Events (Continued) i Event Date/ Time I APRM Calibration Oct 22/0159 l SP-2079 Thermal Limits Evaluation Oct 22/0059 l
SP-2077 Control Valve Surveillance Test Oct 22/0159 l i
SP-2076 Stop Valve Surveillance Test Oct 22/0159 SP-2081 Rerate Chemistry Oct 22/0259 SP-2082 Steady State Data Collection Oct 22/0259 Test Plateau B Results Approved Oct 22/0359 l l
Increased Power to 97% (Test Condition 5) Oct 22/0359 SP-2076 Stop Valve Surveillance Test Oct 22/0459 SP-2077 Control Valve Surveillance Test Oct 22/0459 HP-C-200 Radiation Measurements Oct 22/0559 APRM Calibration Oct 22/0559 j SP-2075 Pressure Regulator Stability Oct 22/0559 SP-2082 Steady State Data Collection Oct 22/0659 SP-2079 Thermal Limits Evaluation Oct 22/0659 Dropped power to 86.6's due to loss of Oct 22/0759 220-34 Startup Feed. Power drop and recovery was via recirc flow i SP-2074 Feedwater Stability Oct 22/1159 l Test Plateau C Results Approved Oct 22/1259 Increased Power to 100% (Test Condition 6) Oct 22/1859 HP-C-200 Radiation Measurements Oct 22/2059 l
Oct 22/1959 Drywell Temperature Monitoring Test SP-2082 Steady State Data Collection Oct 22/2059 SP-2081 Rerate Chemistry Oct 22/2259 SP-2079 Thermal Limits Evaluation Oct 22/2059 i
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,, , Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 9 of 55 5.0 Chronology of Events (Continued)
Event Date/ Time Feedwater Heater Level Controller Adjustments Oct 23/0259 SP-2076 Stop Valve Surveillance Test Oct'23/0959 SP-2077 Control Valve Surveillance Test Oct 23/1059 i i
SP-2056 Containment Noise Monitoring Oct 23/1340 RE-27 TIP Reproducibility Oct 23/2159 ;
i Core Flow Verification Oct 23/2259 LPRM Gain Calibration Oct 24/0559 APRM Calibration Oct 24/0659 l
Drop to 75% power via recirc flow Oct 24/2100 1 I
Full power target rod pattern pattern set Oct 24/2300 '
Unit back to 100% power Oct 25/0500 SP-2068 RCIC Stability at Rerated Pressure Oct 26/0559 SP-2072 HPCI Cold Quick Start Oct 26/0559 SP-2070 HPCI Stability at Rerated Pressure Oct 26/0559 ,
1 SP-2069 RCIC Cold Quick Start Oct 29/0959 SP-2078 Thermal Performance Data Collection (9 Day Soak Complete) Nov 1/0800 Test Plateau D Results Approved Nov 1/1000
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' ' Peach Bottom Atomic Power Station '
Unit 3 Rerate Startup Test Report Page 10 of 55 TABLE 1 -
Tests Performed for Power Rerate Test Condition Test Description 1 2 3 4 5 6 1 Chemical & Radiochemical X X 2 Radiation Measurements X X X X 4 Shutdown Margin X 5A CRD Insert / Withdraw Times X 5B CRD Scram Timing X 11 LPRM Calibration X 12 APRM Calibration X X X X X X 14B RCIC (> 920#) X 14C RCIC Stability (Rerated X Pressure) 14D RCIC Cold Quick Start X 15B HPCI (> 920#) X 15C HPCI Stability (Rerated X Pressure) 15D HPCI Cold Quick Start X 18 Core Power Distribution X 19 Core Performance X X X X 22 Pressure Regulator 2 X X 23A Feedwater Level Control X X 25 Main Steam Isolacion X valves 33 Turbine Stop Valve ST X X X X
, 34 Turbine Control Valve ST X X X X 35 Recirc. System Flow X Calibration '
72 Drywell Atmospheric X X Cooling 80 Thermal Performance Test X X 81 I&C Surveillance Tests 2 X 82 Steady State Data X X X X X Collection 1 -Pressure Regulator stability checks are performed at approximate rerate power levels of 25% and 97%
2 -These are to be performed prior to the plant condition for which the instrument is required to be operable.
s Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report -
Page 11 of 55 FIGURE 1 Rerate Power / Flow Map 130 -
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Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 12 of 55 1
FIGURE 2 RCIC Acceptance Criteria Curves for Capacity and Actuation
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,, Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 13 of 55 6.0 Test Results Summaries STARTUP TEST 1 - CHEMICAL AND RADIOCHEMICAL l l
Purpose The primary objective of this test is to maintain control of and knowledge about the quality of the reactor coolant chemistry.
Description Chemical and radiochemical samples are taken in accordance with the following plant procedures throughout power ascension to rerated conditions. Specific criteria evaluation for rerated conditions is performed in Special Procedure SP-2081 at the original 100% power level (Test Condition 4) and at the rerate 100% power level (Test Condition 6).
ST-C-095-819-3 ST-C-095-823-3 ST-C-095-864-3 ST-C-095-857-3 ST-C-095-859-3 ST-C-095-822-3 ST-C-095-825-3 ST-C-095-820-3 In addition, normal plant chemistry sampling is performed in accordance with CH-10. A Flag File Report, run at 95% (original 100%) and 100% rerate power, summarizes the chemistry data obtained, compares the values to plant requirements and flags any parameters which exceed their specific limit. If possible, carryover is determined at 95% and 100% using normally obtained grab samples. The Flag File data and the carryover determination l are performed to obtain baseline data and have no acceptance criteria specifically associated with them.
Level 1 Criteria
- 1. Primary Reactor Coolant iodine dose equivalent I-131 concentration is less than or equal to 0.2 microcurie / gram.
- 2. Primary Coolant conductivity is less than or equal to 5.0 micromhos/cm at 25 C.
- 3. Primary Coolant chloride ion concentration is less than or equal to 200 ppb.
- 4. Noble gas release rate from the Steam Jet Air Ejector discharge shall not exceed 320,000 microcuries/second af ter a ,
30 minute decay. I
- 5. Site Tech Spec Dose Rate < 100%.
Level 2 Criteria None.
Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report l Page 14 of 55 l STARTUP TEST 1 - CHEMICAL AND RADIOCHEMICAL (Continued) '
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Results l Special Procedure SP-2081, Chemistry Rerate Information, was i performed at 95% and 100% power levels. Samples were obtained and '
analyzed. All acceptance criteria were satisfied. The test results are shown in Table 1.1.
TABLE 1.1 Rerate Chemistry Results l
Actual Data Actual Data Acceptance Parameter (95%) (100%) Criteria
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Primary Reactor Coolant Iodine 8.42x10" 7.406x10" s 0.2pCI/gm Primary Reactor Coolant s 5.0 Conductivity 0.099 0.093 gmhos/cm Chloride Ion Concentration 1.7 1.336 s 200 ppb Noble Gas s 320,000 Release Rate 8,475 12,252 gCi/sec Noble Gas Dose Rate < 30% < 30% < 100%
i A Flag File Report was run at 95% and 100% rerate power which summarized the chemistry data obtained, compared the values to plant requirements and flagged any parameters which exceeded their specific limit. All flag file action codes were "500s" and therefore no actions were required. ;
l Carryover was not able to be determined at 95% power since I-131 was not detected in the reactor water or condensate influent samples. Carryover was 4.8 at 100% power. Carryover is determined for baseline data only.
There are no criteria associated with carryover.
In general, chemistry has not shown any significant changes due to power rerate.
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( ,, , Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 15 of 55 STARTUP TEST 2 - RADIATION MEASUREMENTS l
Purpose This test measures radiation levels at selected locations and power conditions to assure the protection of plant personnel and continuous compliance with guideline standards of 10CFR20 during plant operation.
Descriotion Radiation levels are measured at various locations in the plant at l rerated power levels of 90%, 95%, 98%, and 100% (Test Conditions 3, 4, 5, and 6, respectively) in accordance with HP-C-200.
Level 1 Criteria Radiation doses of plant origin and occupancy times of personnel in radiation zones shall be controlled consistent with the guidelines of the standards for protection against radiation outlined in 10CFR20 NRC General Design Criteria.
Level 2 Criteria l
None.
Results Radiation surveys were conducted at rerated power levels of 90%, 95%,
l 98%, and 100% in accordance with HP-C-200. The results of these surveys are shown in Table 2.1. In addition, surveys were conducted during Reactor Core Isolation Cooling (RCIC), High Pressure Coolant Injection l (HPCI), and Residual Heat Removal (RHR) system runs. These results are shown in Tables 2.2 and 2.3, respectively.
Essentially, the dose rates are the same as those experienced at the original 100% power. The Main Turbine Deck is the only area experiencing increased dose rates. No area postings were changed as a result of achieving the rerate 100% power level.
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i - A Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report i Page 16 of 55 i
STARTUP TEST 2 - RADIATION MEASUREMENTS (Continued)
TABLE 2.1 Rerate Radiation Survey Results (Dose Rates Recorded in mrem / Hour)
Rerate Power Level Plant Location 90 95 97 100 Outside A SJAE <2 <2 <2 <2 l Outside B SJAE <2 <2 <2 <2 Outside Mech Vac Pp Rm <2 <2 <2 <2 Moisture Separator Area 440 500 600 600 4A FW Heater Room 10 14 12 10 4B FW Heater Room 30 38 36 36 4C FW Heater Room 6 6 8 8 TB Fan Room -El 195 <2 <2 <2 <2-A RFPT Room 150 180. 180 200 B RFPT Room 140 160 160 180 C RFPT Room 140 150 160 160 5A FW Heater Room 80 100 100 120 5B FW Heater Room 80 80 100 100 SC FW Heater Room 60 80 80 80 TB El 165 General Area <2 <2 <2 <2 Turbine Deck 400 460 480 600 Outside - Fence Area <0.1 <.2 <.2 <.2
_Drywell Equip. Hatch Door 1.0 1.0 1.0 1.0 TIP Room Door 0.3 0.4 0.4 0.4 Drywell Personnel Airlock 8.0 10 10 10 )
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.. 6 Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 17 of 55 STARTUP TEST 2 - RADIATION MEASUREMENTS (Continued)
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1 TABLE 2.2 I Radiation Surveys During RCIC and HPCI System Runs l Plant Location Rerate Power Level = 100%
RCIC System Run HPCI System Run RCIC Room 40-60 mrem /hr <2 mrem /hr HPCI Room NA 44 mrem /hr I l
Torus Room 5-140 mrem /hr 4-300 mrem /hr l North Isolation Valve Room NA 6-200 mrem /hr South Isolation Valve Room NA 2-12 mrem /hr l
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6 Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 18 of 55 STARTUP TEST 4 - SHUTDOWN MARGIN Purpose This test demonstrates that the reactor will be subcritical by at least 0.38% (delta K) /K throughout the fuel cycle with any single control rod fully withdrawn.
Description Shutdown margin demonstration is performed in accordance with ST-R-002-910-3, Shutdown Margin, during Test Condition 1.
Level 1 Criteria Shutdown margin is 20.38% (delta K) /K + R.
Level 2 Criteria None.
Results For Unit 3 Cycle 11, the required shutdown margin must be greater than 0.38% (delta K)/K + R, where R is equal to 0.960% (delta K) /K.
Therefore, the calculated shutdown margin for Cycle 11 must be greater than 1.340% (delta K) /K.
As Unit 3 reached criticality, data was collected to calculate Shutdown Margin in accordance with ST-R-0 02 - 910-3, Shutdown Margin (Unit 3 -
Cyc!t 11). Cycle 11 shutdown margin was determined to be 1.9%
(delta K)/K. This satisfies the Level 1 Acceptance Criteria.
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,, , Peach Bottom Atomic Power Station l Unit 3 Rerate Startup Test Report Page 19 of 55 STARTUP TEST 5A - CONTROL ROD DRIVES - Insert / Withdraw Timing Purpose j This testing demonstrates that the control rods meet Technical )
Specification requirements for RPIS full in, RPIS full out, and i uncoupling checks.
Description Control rod insert / withdraw timing is conducted during Test Condition 1 in accordance with ST-O-003-465-3, Control Rod Withdraw Tests.
1 Level 1 Criteria l I
RPIS Full in, RPIS Full out, and uncoupling checks are completed !
satisfactory for all control rods.
Level 2 Criteria Insert and withdraw stroke times correlate to 3 inches per second or one position per second.
l Results l 1
All control rods were stroked and couple checked in accordance with ST- !
O-003-465-3. Level 1 Acceptance Criteria was satisfied for all control rods. RT-O-003-990-3, Control Rod Speed Adjustment, was used to stroke j time the control rods that maintenance was performed on or rods that 1 operators visually appeared to be slow or fast. Rods that were l determined to be slow or fast were adjusted via the directional control l valve needle valve. After the adjustments, the rod speeds were acceptable. Therefore, the Level 2_ criteria was met prior to startup and no Test Exception Report was required.
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.. k Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 20 of 55 STARTUP TEST 5B - CONTROL ROD DRIVES - Scram Timing Purcosa This testing demonstrates that the control rods meet Technical Specification 1.cQuirements for scram times.
Descriotion Scram timing of control rods is performed during Test Condition 1 in accordance with ST-R-003-460-3, CRD Scram Insertion Timing, Full In and Full Out Position Indication Check, and Rod Coupling Integrity Check For All Operable Control Rods.
Level 1 Criteria
- 1. The total average 5% scram time is less than or equal to 0.375 seconds.
- 2. The total average 20% scram time is less than or equal to 0.90 seconds.
- 3. The total average 50% scram time is less than or equal to 2.0 seconds.
- 4. The total average 90% scram time is less than or equal to 3.5 seconds.
- 5. The avercge 5% scram insertion times for the three fastest control rods of 'l groc,a of four control rods in a two by two array is less than or equal to 0.398 seconds.
- 6. The average 20% scram insertion times for the three fastest control l rods of all groups of four control rods in a two by two array is l less than or equal to 0.954 seconds. j
- 7. The average 50% scram insertion times for the three f astest control rods of all groups of four control rods in a two by two array is less than or equal to 2.120 seconds.
- 8. The average 90% scram insertion times for the three fastest control rods of all groups of four control rods in a two by two array is less than o' equal to 3.8 seconds.
- 9. Insertion tirae to 90% of all operable control rods is less than or equal to 7.00 seconds.
Level 2 Criteria None.
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- Peach Bottom Atomic Power-Station Unit 3 Rerate Startup Test Report Page 21 of 55 STARTUP TEST 5B - CONTROL ROD DRIVES - Scram Timing (Continued)
Results Scram timing was performed for all control rods. All Level 1 Acceptance Criteria were satisfied. Test results are shown in Table 5B.1. Test results for the average scram insertion times for the three fastest rods of all groups of four control rods in a two by two array are given as the most limiting time for the two by two arrays. The acceptance criteria, as defined above, is adjusted within the test procedure to account for the difference between actual notch location and percentage ,
of rod insertion. The adjusted acceptance criteria is shown below with the test results.
t TABLE 5B.1 CRD Scram Timing Results Acceptance Test Scram Time Description Criteria Results (Seconds) (Seconds) 1 Total Average 5% scram time s 0.359 0.346 Total Average 20% scram time s 0.92 0.743 Total Average 50% scram time s 1.99 1.490 Total Average 90% scram time s 3.67 2.628 Average 5% scram insertion times for the three fastest control rods of all groups of four control rods in a two by two array s 0.382 0.369 Average 20% scram insertion times for the three fastest control rods of all groups of four control rods in a two by two array s 0.974 0.782 Average 50% scram insertion times for the three fastest control rods of all groups of four control rods in a two by two array s 2.110 1.561 Average 90% scram insertion times for the three fastest control rods of all groups of four control rods in a two by two array s 3.970 2.730
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.. A j ,, . Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report 4
Page 22 of 55 j STARTUP TEST 11 - LPRM CALIBRATION Purpose The purpose of this test is to calibrate the local power range monitors (LPRMs).
) Description
! The LPRM channels are calibrated to make the LPRM readings proportional
, to the neutron flux in the narrow-narrow water gap at the chamber elevation. This calibration is performed in accordance with ST-I-60A-230-3 LPRM Gain Calibration, during Test Condition 6.
Level 1 Criteria All operable LPRM values are within 2 absolute value points of the last P-1 LPRM RCAL (Calibrated LPRM Readings) values.
Level 2 Criteria None.
Results Using the Plant Monitoring System (PMS) and 3-D Monicore System, all operable LPRMs were successfully calibrated. All operable LPRM raw l readings were within 2 absolute value points of the last P-1 Calibrated l LPRM values. LPRM Gain Adjustment Factor (GAFT) values for all operable LPRM channels were greater than or equal to 0.95 and less than or equal to 1.05, as required.
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Peach Bottom Atomic Power Station 3
Unit 3 Rerate Startup Test Report Page 23 of 55 i
STARTUP TEST 12 - APRM CALIBRATION Purnose The purpose of this test is to calibrate the average power range monitors (APRMs).
Descriotion Each APRM channel reading is adjusted to be consistent with the incidated core thermal power. This calibration is performed as necessary during power ascension in accordance with ST-O-60A-210-3, APRM System Calibration During Two Loop Operation, or RT-R-60A-210-3, APRM Gain Adjustment.
Level 1 Criteria APRMs are correctly set to calculated APRM setting. l 1
Level 2 Criteria None.
Results APRM Calibrations or Gain Adjustments were performed during each Test Condition (1 through 6) during the Rerate Startup Test Proyeam to ensure the following:
1
- 2. The corresponding APRM gain adjustment factors (AGAF) values on the 3D MONICORE P1 edit are s 1.00.
Each performance of ST-O-60A-210-3, APRM System Calibration During Two Loop Operation, and RT-R-60A-210-3, APRM Gain Adjustment, was completed satisfactorily. No problems were encountered during these tests.
.. i Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 24.of 55 STARTUP TEST 14 - REACTOR CORE ISOLATION COOLING SYSTEM Purpose This testing verifies proper operation of the Reactor Core Isolation Cooling (RCIC) System at the rerate operating pressure and provides baseline data for future surveillance testing. This testing is separated into three subtests (Startup Test Instructions, STI-14B, -14C, and -14D). Data obtained during the rated pressure quick start test is analyzed to verify the margin to trip on RCIC Turbine Speed following a quick start to satisfy SIL 377 commitment.
Descriotion STI-14B Using the current controller settings, RCIC is operated in the CST to CST mode with reactor pressure between 920 psig and 1000 psig to j demonstrate acceptable operation at the lower end of the operating ;
pressure range for power rerate and to provide a benchmark to which future surveillance tests are compared. This demonstration is performed i using ST-O-013-301-3, RCIC Pump, Valve, Flow and Unit Cooler Functional and In-Service Test, and Special Procedure SP-2067. A stability check of the RCIC system is also performed during this test by introducing small flow steps following the system quick start.
e STI-14C j System stability at 100% rerated operating pressure shall be demonstrated by introducing small step disturbances in flow demand in accordance with RT-X-013-230-3 and Special Procedure SP-2068. l Additionally, the RCIC Pump, Valve, Flow and Unit Cooler Functional and In-Service was performed.
STI-14D A cold quick start is performed in accordance with RT-0-013-725-3, RCIC Response Time Test and Special Procedure SP-2069 at 100% rerate power.
As part of the analysis of the RCIC cold quick start at rerated conditions, the margin to trip on RCIC turbine speed is measured to determine if the recommended modification of GE SIL 377 is needed.
a,-s- w -
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Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 25 of 55 STARTUP TEST 14 - RCIC SYSTEM (Continued)
Level 1 Criteria
- 1. The system shall deliver rated flow (600 gpm) in less than or equal to the amount of time defined by the curve in Figure 2 from the
. automatic initiation at any reactor pressure between 150 psig and rated pressure at rerate conditions.
- 2. The RCIC turbine shall not trip or isolate during auto or manual starts.
NOTE: If any Level 1 criteria are not met, the reactor will only be allowed to operate up to a restricted power level defined by Figure 2 until the Level 1 criteria are met. Consult Technical Specifications for other actions to be taken.
Level 2 Criteria
- 1. To provide an overspeed and isolation trip avoidance margin, the transient start first and subsequent speed peaks shall not be more than 5% faster than rated RCIC turbine speed.(Peak speed s 4777.5 rpm)
- 2. The speed and flow control loops shall be adjusted so that the decay ratio of any RCIC system related variable is less than 0.25.
- 3. Turbine gland seal condenser system shall be capable of preventing steam leakage to the atmosphere.
Results STI-14B With reactor pressure at approximately 954 psig, RCIC system stability was verified by introducing a 400 rpm speed decrease step followed by a 400 rpm speed increase step. Plots of the step inputs showed good system response. No controller adjustments were required. Then a 60 gpm flow increase and a 60 gpm flow decrease was introduced. As before, no controller adjustments were required. The RCIC Pump, Valve, Flow and Unit Cooler Functional passed with no actions required. ;
I Following these tests, RCIC was shut down, and a quick start was j performed. RCIC achieved rated flow of 600 gpm in 21.8 seconds with a j pump discharge pressure of 1275 psig. All Level 1 and Level 2 '
acceptance criteria were satisfied.
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Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 26 of:55 STARTUP TEST 14 - RCIC SYSTEM (Continued)
STI-14C and STI-14D At approximately 99.7% rerated reactor power and 1029 psig reactor pressure, a RCIC cold quick start was initiated. Rated flow (600 gpm) was attained in 17.1 seconds with a pump discharge pressure of 1312 psig. - Peak RCIC turbine speed during the quick start was 4550. rpm. All Level 1 and Level 2 acceptance criteria were satisfied. Based on the acceptable RCIC: speed peaks during the quick start at rerated conditions, the modification recommended by GE SIL 377 is not required.
Immediately following the cold quick start at rated conditions, RCIC system stability was checked. RCIC system stability was verified by introducing a 400 rpm speed decrease step followed by a 400 rpm speed increase step. Plots of the step inputs showed good system response.
No controller adjustments were required. Then, a 60 gpm flow decrease and a 60 gpm flow increase were introduced. As before, no controller adjustments were required. The RCIC Pump, Valve, Flow and Unit Cooler Functional passed with no actions required.
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,* , Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 27 of 55 STARTUP TEST 15 - HIGH PRESSURE COOLANT INJECTION SYSTEM Purpose This test verifies proper operation of the High Pressure Coolant Injection (HPCI) System at the rerate operating pressure and provides baseline data for future surveillance testing. This testing is separated into three subtests (Startup Test Instructions, STI-15B, -15C, and -15D).
Descriotion STI-15B Using the current controller settings, HPCI is operated in the CST to CST mode with reactor pressure between 920 psig and 1000 psig to demonstrate acceptable operation at the lower end of the operating pressure range for power rerate and to provide a benchmark to which future surveillance tests are compared. This demonstration will be performed using ST-O-023-301-3, HPCI Pump, Valve, Flow and Unit Cooler Functional and In-Service Test and Special Procedure SP-2071. A stability check of the HPCI system is also performed by introducing small flow steps following the system quick start.
STI-15C System stability at rerated operating pressure shall be demonstrated by introducing small step disturbances in flow demand in accordance with RT-X-023-210-3 and Special Procedure SP-2070.
STI-15D A cold quick start is performed in accordance with RT-O-023-725-3, HPCI Response Time Test and Special Procedure SP-2072 at 100% rerate power.
Level 1 Criteria
- 1. The system shall deliver rated flow (5000 gpm) in less than or equal to 30 seconds from the automatic initiation at any reactor pressure between 150 psig and rated pressure at rerate conditions.
- 2. The HPCI turbine shall not trip or isolate during auto or manual starts.
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.* . Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 28 of 55 ,
STARTUP TEST 15 - HIGH PRESSURE COOLANT INJECTION SYSTEM (Continued)
Level 2 Criteria
- 1. To provide an overspeed and isolation trip avoidance margin, the transient start first speed peak shall not be within 15% (of rated turbine speed) of the overspeed trip, and subsequent speed peaks shall not be more than 5% faster than rated HPCI turbine speed. l
- 2. The speed and flow control loops shall be adjusted so that the decay ratio of any HPCI system related variable is not greater than 0.25.
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- 3. Turbine gland seal condenser system shall be capable of preventing steam leakage to the atmosphere.
Results STI-15B With reactor pressure at approximately 947 psig, HPCI system stability l was verified by introducing a 400 rpm speed decrease followed by a 400
( rpm speed increase. Plots of the speed changes showed good system response. No controller adjustments were required. Following the speed {
I changes, a 500 gpm negative flow step followed by a 500 gpm positive I flow step. Plots of the step inputs showed good system response. No controller adjustments were required. 1 Following the stability check, HPCI was shut down, and a quick start was performed. HPCI achieved rated flow of 5000 gpm in less than 30 seconds.
The transient start first turbine speed peak was 2650 rpm. The second l and only subsequent speed peak was 3300 rpm. Both speed peaks satisfied the acceptance criteria requiring peak speeds to be less than or equal to 4385 rpm and 4305 rpm, respectively. All Level 1 and Level 2 acceptance criteria were satisfied.
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Peach Bottom Atomic Power Station l Unit 3 Rerate Startup Test Report Page 29 of 55 STARTUP TEST 15 - HIGH PRESSURE COOLANT INJECTION SYSTEM (Continued)
STI-15C and STI-15D l On October 22, 1995 at approximately 99.2% rerated reactor power and 1032 psig reactor pressure, a HPCI cold quick start was initiated.
Rated flow (5000 gpm) was attained in less than 30 seconds. All speed peaks were less than their respective acceptance criteria. This test was reperformed after greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> due to controller adjustments made during the stability check. Greater detail is provided in the second cold quick start description following the initial stability check description.
Immediately following the cold quick start at rated conditions, HPCI system stability was checked. HPCI system stability was verified by introducing a 400 rpm speed decrease followed by a 400 rpm speed increase. Plots of the speed changes were analyzed and indicated minor EGR changes were necessary. Following the EGR adjustments, the same speed changes were introduced and a 500 gpm flow decrease and a 500 gpm flow increase were introduced. Plots of these changes showed good l system response and no further adjustments were necessary. Even though l the initial cold quick start passed the acceptance criteria, due to the controller adjustments during the initial stability test, the system was then shut down for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to reperform the cold quick start.
On October 26, 1995 at approximately 99.8% rerated reactor power and 1029 psig reactor pressure, the HPCI cold quick start was reperformed.
Rated flow of 5000 gpm was attained in 22.6 seconds with a pump discharge pressure of 1312.5 psig. The initial speed peek was 750 rpm.
There was no additional speed peek and speed ramped smoothly to 3750 rpm. The speed peek was well below the acceptance criteria of 4385 rpm.
The stability test was reperformed with the same speed and flow changes.
Plots of these changes showed good system response. No adjustments were required. The HPCI Pump, Valve, Flow and Unit Cooler Functional was performed with ST-O-023-301-3. All ST requirements were met.
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l Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 30 of 55 STARTUP TEST 18 - CORE POWER DISTRIBUTION Purpose This test confirms both the reproducibility of the traversing incore probe system (TIPS) readings and core power distribution symmetry.
Descrintion This test is performed at Test Condition 6 in accordance with RE-27, Core Power Symmetry and TIP Reproducibility, and FM-UG-412, Analysis of Total TIP Uncertainty Using NSTIP.
Level 1 Criteria None.
Level 2 Criteria )
l
- 1. The Total TIP uncertainty is < 7.1%. l
- 2. The TIP traces shall be reproducible within 3.5% relative error.
Results l
At approximately 99.3% power, reactor power distribution data was I collected by repeatedly traversing the core axially with gamma TIPS. The l data was subsequently processed by the Plant Monitoring System computer ,
programs and 3D Monicore and transmitted to the Fuel & Services Division for analysis. Results of the analysis determined the maximum total TIP uncertainty to be 2.248% which satisfies the requirement to be less than 7.1%. The TIP traces were found to be reproducible within 3.5% relative .
error. All acceptance criteria were satisfied.
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Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 31 of 55 STARTUP TEST 19 - CORE PERFORMANCE I
Purpose I l
This test evaluates the core performance parameters to assure plant thermal limits are maintained during the ascension to rerate conditions.
Description )
As power is increased along a constant rod pattern line, core thermal ,
power will be measured near 90% (Test Condition 3), 95% (Test Condition i 4), 97% (Test Condition 5), and at 100% rerate power (Test Condition 6) , j using the current plant methods of monitoring reactor power. )
i Demonstration of fuel thermal margin is performed prior to, during and following power ascension to each power level up to the rerated 100%
power. Fuel thermal margin is projected for the next test point to l confirm acceptable margin, and is satisfactorily verified by the measurements taken at each test point before advancing to the next increment.
This on-going monitoring of fuel conditions is performed in accordance with RE-31, Reactor Engineering Core Monitoring Instructions and Special Procedure SP-2031, Core Performance Thermal Limits Evaluation.
Level 1 Criteria The following thermal limits are s 1.000:
- 1. Maximum MFLPD (Core Maximum Fraction of Limiting Power Density)
- 2. Maximum MFLCPR (Core Maximum Fraction of Limiting Critical Power)
- 3. Maximum MAPRAT (Core Maximum Average Planar Linear Heat ,
Generation Rate Ratio) !
- 4. FLLLP (Fraction of Load Line Limit Power Level 2 Criteria None.
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.. o-Peach-Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 32 of 55 STARTUP TEST 19 --CORE PERFORMANCE (Continued)
Results Using the Plant Monitoring System (PMS) computer and 3D Monicore, data was obtained to project fuel thermal margin at each subsequent test condition and to evaluate thermal limits at each test condition corresponding to approximate reactor power levels of 90%, 95%, 97%, and 100%. The results at each test condition are shown in Table 19.1. All acceptance criteria were satisfied.
TABLE 19.1 Core Performance - Thermal Limits Evaluation Results Rerate Power Level Thermal Limit 90% 95% 97% 100%
MFLCPR s 1.000 0.956 0.945 0.941 0.975 MFLPD s 1.000 0.885 0.932 0.942 0.922 MAPRAT s 1.000 0.930 0.945 0.944 0.912 FLLLP s 1.000 0.894 0.858 0.856 0.923
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, 4 Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 33 of 55
-STARTUP TEST 22 - PRESSURE REGULATOR Purpose j This test has three objectives.
- 1. To confirm the adequacy of the settings for the pressure control loop by analysis of the transients induced in the reactor pressure control system by means of the pressure regulators.
- 2. To demonstrate the backup capability of the pressure regulators via simulated failure of the controlling pressure regulator.
- 3. To demonstrate that other af fected parameters are within acceptable limits during pressure induced transient maneuvers.
Descrintion At approximate power levels of 25%, and 97% (Test Conditions 1, and 5),
the following step inputs (approximate values) will be made to the controlling pressure regulator:
- 1. -3 psi
- 2. +3 psi
- 3. -5 psi
- 4. +5 psi
- 5. -10 psi
- 6. +10 psi When this testing is complete for one pressure regulator, transfer is made to the other pressure regulator, and the steps shall be repeated.
Simulated failure of each pressure regulator, while in control, is then performed to demonstrate the backup pressure regulator capability.
Transfer between pressure regulators by normal transfer and by simulated failure demonstrate that these events are survivable and well-behaved.
The step inputs and failover testing is performed in accordance with Special Procedure SP-2075.
Total steam flow and pressure regulator output data is taken in increments of 5% power during the power ascension from 25% to 85%
rerated power and in increments of 2% from 85% to 100% rerate power. The ,
variation in the slope of the curve plotted on linear graph paper 1 (pressure regulator output versus total steam flow) must show that the incremental regulation is within the criteria. If the requirements are not met, the control valve function generator break points will have to be adjusted. Incremental regulation is determined in accordance with Special Procedure SP-2084.
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.. L Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 34 of 55 STARTUP TEST 22 - PRESSURE REGULATOR (Continued)
Level 1 Criteria The transient response of any pressure control system related variable to any test input must not diverge.
Level 2 Criteria l
- 1. Pressure control system related variables may contain oscillatory modes of response. In these cases, the decay ratio for each controlled mode of response must be less than or equal to 0.25. l (This criterion does not apply to tests involving simulated failure i of one regulator with the backup regulator taking over.) l
- 2. The pressure response time from initiation of pressure setpoint change to the turbine inlet pressure peak shall be s 10 seconda. l 1
- 3. Pressure control system deadband, delay, etc., shall be small enough that steady state limit cycles (if any) shall produce steam i flow variations no larger than +0.5% of rated steam flow. )
- 4. The peak neutron flux and/or peak vessel pressure shall remain below the scram settings by 7.5% and 10 psi respectively for all .
pressure regulator transients.
- 5. The variation in incremental regulation (ratio of the maximum to the minimum value of the quantity, " incremental change in pressure ;
control signal / incremental change in steam flow", for each flow range) shall meet the following:
% of Steam Flow Obtained With Valves Wide Open Variation 0 to 85% s 4:1 85% to 97% s 2:1 85% to 99% s 5:1 Results Pressure Regulator Stability Pressure Regulator Stability testing was performed at rerate power levels of 24%, 97.9%. The data obtained during each test condition is summarized in Tables 22.1 and 22.2. The system response to all size step changes at each power level was excellent. There were no signs of process divergence or oscillations. Pressure response time and margins to scram setpoints were satisfactory in all cases. No limit cycles were observed. All Level 1 and Level 2 acceptance criteria applicable to the stability testing were satisfied.
L Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 35 of 55 STARTUP TEST 22 - PRESSURE REGULATOR (Continued)
, Results (Continued) l
! Pressure Regulator Stability Pressure Regulator failovers were performed at rerate power levels of 24% and 97.9%. The data obtained during each test condition is summarized in Tables 22.3 and 22.4. In all cases, the backup pressure
, regulator took control when the controlling regulator was failed. All l acceptance criteria were satisfied.
Pressure Regulator Incremental Regulation Determination Pressure Regulator Controller Output and steam flow data was collected approximately every 5% increase power from 25% to 85% power. From 85%
power to 100% power the data was taken every 2% power increase. This data was used to calculate the pressure regulator incremental regulation. Experience gained from Unit 2 indicated that data below 25%
power was not valid due to plant configurations (i.e., turbine not on line, bypass valve jack open signal). Therefore, 25% power was chosen as the starting point.
Data taken for this test was valid and calculations showed that the variation in incremental regulation oatisfied the acceptance criteria for each cteam flow range.
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Peach Bottom Atomic Power Station
, Unit 3 Rerate Startup Test Report Page 36 of 55 f
STARTUP TEST 22 - PRESSURE REGULATOR (Continued)
TABLE 22.1
'A' PRESSURE REGULATOR STEP CHANGE DATA i
Rorate Step Peak Pressure Peak Steady Power Size Pressure Response Power State Level (+/-) (psig) Time (%) Cycles
-3 937 3.4 23.58 0
+3 937.5 4.5 23.58 0
-5 935.0 3.3 23.4 0
+5 940 3.3 28.1 0 23.5%
-10 935 3.6 21.9 0
+10 948 3.4 29.7 0
-3 1025 <4 96.0 0 i
+3 1031 <4 98.5 0
-5 1023 <4 99.0 0
+5 1033 <4 100 0 97.9%
-9 1020 <4 94.0 0
+9 1038 <4 101 0
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Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 37 of 55 STARTUP TEST 22 - PRESSURE REGULATOR (Continued)
TABLE 22.2
'B' PRESSURE REGULATOR STEP CHANGS DATA Rerate Step Peak Pressure Peak Steady l Power Size Pressure Response Power State l Level (+/-) (psig) Time (%) Cycles
-3 940 3.7 24.2 0 ;
+3 948 3.1 27.3 0 l 1
-5 933 3.5 23.4 0 1
+5 948 3.4 28.1 0 l 23.5 1
-10 935 3.7 21.9 0
+10 948 3.5 28.9 0
-3 1026 <4 96.5 0
+3 1030 <4 98.5 0 g
-5 1023 <4 95.0 0
+5 1033 <4 100 0
-10 1021 <4 93.5 0
+10 1036 <4 101.5 0 l
Peach Bottcm Atomic Power Station Unit 3 Rerate Startup Test Report Page 38 of 55 STARTUP TEST 22 - PRESSURE REGULATOR (Continued)
TABLE 22.3 Pressure Regulator 'B' Failed PRESSURE REGULATOR FAILOVER DATA Rerate Step Peak Pressure Peak Steady Fower Size Pressure Response Power State Level (psi) (psig) Time (%) Cycles 24% 3 955 <.5 32.8 2 97% 3 1035 <4 104 1 TABLE 22.4 Pressure Regulator 'A' Failed PRESSURE REGULATOR FAILOVER DATA Rerate Step Peak Pressure Peak Steady Power Size Pressure Response Power State Level (psi) (psig) Time (%) Cycles 24% 3 955 <.5 33.6 2 97% 3 1035 <4 104 1 TABLE 22.5 Incremental Regulation Determination (Spreadsheet Calculation)
I Steam Flow Incremental Regulation Variation Level 2 Rangs Max / Min Criteria 0% to 85% 1.09 0.645 1.69 s 4:1 85% to 97% 1.44 0.769 1.87 s 2:1 85% to 99% n/a* m/a* n/a* s 5:1
- Steam flow as defined in the test is in percent of valves wide open.
Percent of steam flow did not exceed 91.2%. Valves wide open condition
, will not be achieved during operation; therefore, the values provided from 85% to 97% covers the full range of power operating conditions for steam flow as expressed in % valves wide open.
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Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 39 of 55 STARTUP TEST 23 - FEEDWATER SYSTEM - Water Level Setpoint Changes I
Purpose j
This test verifies that the feedwater system has been adjusted to provide acceptable reactor water level control at rerated conditions. l J
Description l During the 3R10 outage, speed regulation tests are performed on the A, B, and C reactor feedwater pumps in accordance with RT-B-06D-201-3, RT-B-06D-202-3, and RT-B-06D-203-3 to determine the variation in speed regulation between the three pumps.
Reactor water level setpoint changes of approximately 3 to 6 inches are used to evaluate and acceptably adjust, if necessary, the feedwater control system settings for power and feedwater pump modes tested. The level setpoint changes are performed in accordance with RT-I-006-230-3, Feedwater Control System Stability Response Test, and Special Procedure SP-2074. Due to the ARTS /MELLA modifications having been installed in the previa.; outage (3R09), level setpoint changes are performed at 97%
power only. This change from Unit 2 was discussed with and agreed to by i GE.
Level 1 Criteria The transient response of any level control system related variable to any test input shall not diverge.
Level 2 Criteria
- 1. Level control system related variables may contain oscillatory modes of response. In these cases, the decay ratio for each controlled mode of response shall be less than or equal to 0.25.
- 2. At steady state generation for the 3/1 element systems, the input scaling to the mismatch gain shall be adjusted such that level error due to biased mismatch gain output shall be within 1 inch.
- 3. The variation in incremental regulation (ratio of the maximum to the minimum value of the quantity " incremental change in feedwater control signal divided by incremental change in feedwater flow")
does not exceed a factor of 2 to 1.
- 4. The turbine speed regulation variation between the three feedpumps must match within 6% of rated speed.
Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 40 of 55 STARTUP TEST 23 - FEEDWATER - Water Level Setpoint Changes (Continued)
Results Speed Regulation Speed regulation tests were performed on the A, B, and C reactor feedwater pumps during the 3R10 outage. The test procedures contain more conservative criteria than the GE acceptance criteria identified above. Individual feedpump turbine speed regulation must be 6% 1 0.5%,
and the turbine speed regulation variation between the three feedwater pumps must match within il.0%. All acceptance criteria contained in the RT were satisfied.
TABLE 23.1 Reactor Feedwater Pump Turbine Speed Regulation l RT-B-06D-201-3 RT-B-06D-202-3 RT-B-06D-203-3 RFPT A RFPT B RFPT C RFPT i l
- % 5.9 5.7 5.9 i l
RPM /In. 63.40 61.23 64.29 l 1
Feedwater Stability l
Feedwater Stability testing was conducted at 96.7%. Six inch level l setpoint changes were input and system response was monitored. System l l response was not oscillatory and showed no signs of divergence. No system adjustments were required. All acceptance criteria related to system stability were satisfied.
The level error between single and three element level control was also
- verified following the stability testing. At steady state conditions, l
reactor water level was monitored as the Feedwater Level Control System was swapped from single element control to three element control and back to single element control.
There was no noticeable change in reactor water level; therefore, no adjustments to the mismatch gain were necessary. The acceptance criteria was satisfied.
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Peach Bottom Atomic Power Station l Unit 3 Rerate Startup Test Report l Page 41 of 55 .
I STARTUP TEST 25 - MAIN STEAM ISOLATION VALVES I Purpose This test functionally checks each MSIV for proper operation and l measures each valve's closure time. This test also demonstrates that i closure of an MSIV at the normal surveillance test power level (s75%) !
will not cause a reactor scram at rerate conditions. !
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Description !
Individual fast closure of each MSIV is performed in accordance with ST-O-07G-470-3, Main Steam Isolation Valve Closure Timing and Continuity Test, and Special Procedure SP-2073, at approximately 75% power.
Because a significant margin to scram at 71% power was demonstrated in the Unit 2 startup program, the MSIVs were not tested at this conservative power level on Unit 3.
Level 1 Criteria
- 1. MSIV stroke time shall be between 3 and 5 seconds.
Level 2 Criteria
- 1. Reactor pressure must be 20 psi below scram. I (Peak pressure s 1065 psig) l l
- 2. Neutron flux must be 10% below scram.
(Peak power s 110% during 74% power test)
- 3. Steam flow in individual lines must be below the trip setpoint.
(Peak steam flow s 123.3 psid)
Results At approximately 74.1% power, each Main Steam Isolation valve (MSIV) was stroked. The results are shown in Tables 25.1 and 25.2. All acceptance criteria were satisfied. Scram margins were adequate so the test will continue to be performed at not greater than 75% power during the operating cycle.
Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 42 of 55 STARTUP TEST 25 - MAIN STEAM ISOLATION VALVES (Continued)
TABI.3 25.1 MSIV Closures at 74.1% Rorate Power l
MSIV INDIVIDUAL CLOSURE DATA l Close Peak Peak Flux MSIV Time Pressure (Power)
Closed (Seconds) (psig) (%)
AO-3-02-080A 4.02 1026 85.0 AO-3-02-086A 4.26 1027 84.7 AO-3-02-080B 4.19 1024 84.2 AO-3-02-086B 4.00 1023. 85.4 AO-3-02-080C 3.89 1025 84.4 AO-3-02-086C 4.00 1025 86.7 l AO-3-02-080D 4.24 1026 85.7 AO-3-02-086D 4.30 1025 85.5 TABLE 25.2 MSIV Closures at 74.1% Rerate Power MSL Peak Flow (psid)
MSIV MSL A MSL B MSL C MSL D CLOSED AO-2-02-080A 0 55 60.2 62.4 AO-2-02-086A 0 55.8 51.2 62.3 AO-2-02-080B 57.9 0 58.5 61.3 AO-2-02-086B 57.9 0 58.7 60.8 AO-2-02-080C 59.2 54.2 0 62.0 AO-2-02-086C 59.6 54.3 0 62.2 AO-2-02-080D 59.4 55.5 60.8 0 AO-2-02-086D 59.7 55.4 60.9 0
Peach Bottom Atomic Power Station i Unit 3 Rerate Startup Test Report Page 43 of 55 STARTUP TEST 33 - TURBINE STOP VALVE SURVEILLANCE TEST Purcose This test determines the highest power level at which surveillance testing can be performed on the turbine stop valves without causing a reactor scram.
Description Individual main turbine valves are tested routinely during plant operation as required for turbine surveillance testing. Turbine Stop Valves are tested for power rerate in accordance with RT-O-001-400-3 and Special Frocedure SP-2076. Based on the initial results from Test ,
Condition 4 (original 100% power) , this test may be performed during j Test Conditions 5 and 6. '
Level 1 Criteria 4
None. !
l Level 2 Criteria ,
I
- 1. Peak neutron flux must be at least 7.5% below the scram trip setting.
1
- 2. Peak vessel pressure must remain at least 10. psi below the high '
pressure scram setting. (Peak Pressure < 1075 psig)
- 3. Peak steam flow in the main steam lines must remain 10% below the high flow isolation trip setting. (Peak steam flow < 110.97 psid)
Results I
In order to have data from which to extrapolate, Turbine Stop Valve testing was initially performed at 90% power. All acceptance criteria l were satisfied ;' 'therefore , testing could continue at 95% power. The testing at 95% power also satisfied all acceptance criteria. The data from these performances was plotted and extrapolations were performed to determine if testing could be conducted at the subsequent Test Condition (97% power). The extrapolations showed that testing could be performed at 97% power. Testing and susbequent extrapolations at 97% power showed testing could be performed at the 100% rerated power. Testing was again performed at 100% rerated power. All acceptance criteria were met; therefore, future Turbine Stop valve surveillance testing may be performed at 100% power. No load drops are required based on these test results. A summary of the results from all test performances is shown in Tables 33.1, 33.2, and 33.3.
Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 44 of 55 STARTUP TEST 33 - TURBINE STOP VALVE SURVEILLANCE TEST (Continued)
TABLE 33.1 Flux Peaks During Turbine Main Stop Valve (MSV) Closures l l
Actual Test Power Levels (%) I l
90.9 95.7 96.8 99.4 MSV Test Reactor Peak Power (%)
MSV1 93 99.0 102 103.5 MSV2 93 99.0 102 103 MSV3 94 99.5 102 103 MSV4 93 99.0 102 104 TABLE 33.2 i Reactor High Pressure Peaks During MSV Closures Actual Test Power Levels (%)
90.9 95.7 96.8 99.4 MSV Test Reactor Pressure Peak (psig)
MSV1 1024 1034 1036 1034 i I
MSV2 1024 1033 1036 1034 MSV3 1024 1034 1036 1034 MSV4 1024 1033 1036 1034
. b Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 45 of 55 STARTUP TEST 33 - TURBINE STOP VALVE SURVEILLANCE TEST (Continued)
Results (Continued)
TABLE 33.3 MSL Flow Peaks During MSV Closures MSL FLOW Peak (psid)
MSV Test MSL A MSL B MSL C MSL D TEST Power MSV1 Downscale 57.6 58.8 62.7 MSV2 61.4 Downscale 60.2 60.2 MSV3 90.9 58.9 55.0 Downscale 60.2 i
MSV4 58.9 53.8 58.9 Downscale j MSV1 Downscale 62.7 66.6 70.4 MSV2 69.1 Downscale 67.8 65.3 MSV3 95.7 66.6 62.7 Downscale 66.6 MSV4 66.6 61.4 65.3 Downscale MSV1 Downscale 65.3 67.8 71.7 MSV2 70.4 Downscale 69.1 67.8 MSV3 96.8 67.8 62.7 Downscale 69.1 MSV4 67.8 62.7 67.8 Downscale MSV1 Downscale 72.0 74.0 79.2 MSV2 75.2 Downscale 73.6 72.0 MSV3 99 4 72 67.2 Downscale 75.2 MSV4 73.6 65.6 72.8 Downscale
Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 46 of 55 ,
l STARTUP TEST 34 - TURBINE CONTROL VALVE SURVEILLANCE TEST '
Purpose This test determines the highest power level at which surveillance testing can be performed on the turbine control valves without causing a reactor scram.
Descriotion ,
l Individual main turbine valves are tested routinely during plant !
operation as required for turbine surveillance testing. Turbine Control I Valves are individually stroked at various power levels for power rerate in accordance with Special Procedure SP-2077 to determine the highest power at which the normal surveillance testing can be performed. Based on the test results from Test Condition 4 (original 100% power) , this ,
test may be performed during Test Conditions 5 and 6. l l
Level 1 Criteria None.
Level 2 Criteria
- 1. Peak neutron flux must be at least 7.5% below the scram trip setting.
l
- 2. Peak vessel pressure must remain at least 10 psi below the high pressure scram setting. (Peak Pressure < 1075 psig)
- 3. Peak steam flow in each line must remain 10% below the high flow isolation trip setting. (Peak steam flow < 110.97 psid)
Results In order to have data from which to extrapolate, Turbine Control Valve testing was initially performed at 90% power. All acceptance criteria were satisfied; therefore, testing could continue at 95% power. The testing at 95% power also satisfied all acceptance criteria. The data from these performances was plotted and extrapolations were performed to determine if testing could be conducted at the subsequent Test Condition (97% power). The extrapolations showed that testing could be performed at 97% power. Extrapolations at 97% showed that testing could than be performed at 100% power. Minor adjustments to EHC pressure had no effect on predicting that 100% power testing could be performed.
Testing at 100% power was performed and all acceptance criteria was met.
Therefore, testing at 100% power may be performed during cycle operations. No load drops are required based on these test results. A summary of the results from all test performances is shown in Tables 34.1, 34.2, and 34.3.
.s 'a Peach Bottom Atomic Power Station ,
Unit 3 Rerate Startup Test Report i i Page 47 of 55 )
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STARTUP TEST 34 - TURBINE CONTROL VALVE SURVEILLANCE TEST (Continued) 1 TABLE 34.1 Flux Peaks During Turbine Control Valve (TCV) Closures Actual Test Power Levels (%)
89.7 95.9 96.8 99.14 TCV Test Reactor Peak Power (%)
TCV1 90.0 97.0 98.5 101 TCV2 90.0 97.0 99.0 101 TCV3 91.0 97.0 99.0 101 I i
TCV4 91.5 97.0 99.0 101 TABLE 34.2 Reactor High Pressure Peaks During TCV Closures l Actual Test Power Levels (%) !
89.7 95.9 96.8 99.14 TCV Test Reactor Pressure Peak (psig)
TCV1 1008 1025 1028 1027 TCV2 1008 1025 1028 1027 TCV3 1008 1025 1028 1027 TCV4 1008 1025 1028 1027
- - . . - . . . . . . . . . - - - . . . . . - ~ . _ . . - --.-. . . _ ._. - . .- . _ . - -
s 1 Peach Bottom Atomic Power Station
, Unit 3 Rerate Startup Test Report Page 48 of 55 STARTUP TEST 34 - TURBINE CONTROL VALVE SURVEILLANCE TEST (Continued)
Results (Continued)
TABLE 34.3 MSL Flow Peaks During TCV Closures MSL FLOW Peak (psid)
TCV Test MSL A MSL B MSL C MSL D TEST Power TCV1 49.9 46.1 51.2 51.2 TCV2 51.2 46.1 49.9 51.2 TCV3 89.7 49.9 46.1 51.2 51.2 TCV4 51.2 46.1 49.9 51.2 TCV1 56.3 52.5 56.3 57.6 TCV2 56.3 51.2 57.6- 57.6 TCV3 95.9 57.6 51.2 56.3 57.6 TCV4 56.3 51.2 56.3 57.6 TCV1 58.9 53.8 57.6 58.9 TCV2 58.9 53.8 57.6 58.9 TCV3 96.8 58.9 53.8 58.9 58.9 TCV4 58.9 53.8 58.9 60.2 TCV1 60.8 56.0 62.6 62.4 I
TCV2 62.4 56.0 60.8 62.4 TCV3 99.14 62.4 56.0 62.4 62.4 TCV4 62.4 56.0 62.4 64.0 l
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s 1 Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 49 of 55 STARTUP TEST 35 - RECIRCULATION AND JET PUMP INSTRUMENTATION CALIBRATION Purpose The purpose of this test is to perform a complete calibration of the installed recirculation system flow instrumentation including specific signals to the plant process computer.
l Description At operating conditions which allow the recirculation system to operate at the speeds required for rated flow at 100% rerate power, the jet pump flow instrumentation is adjusted to provide correct ficw indication based on the jet pump flow. The total core flow signal to the process computer will be calibrated to accurately read the total core flow.
This calibration of the recirculation system is performed in accordance with RT-I-002-250-3, Core Flow Verification.
Level 1 Criteria None.
Level 2 Criteria
- 1. Total core flow indicated on the Plant Monitoring System (PMS Point B015), Control Room indicator (DPFR-095), and calculated core flow must agree within 2%.
- 2. The percent flow signal to APRM and % core flow calculation numbers must agree within 1%.
Results Core Flow Verification was performed at approximately 100% rerate power and 100% core flow. Data was collected and core flow calculations were performed. All total core flow indications (PMS Point B315, Control Room indicator DPFR-095, and calculated core flow values) agreed within 2%. APRM % flow numbers were also calculated and agreed with % core flow calculation numbers within 1%. All acceptance criteria were satisfied.
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. Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 50 of 55 STARTUP TEST 72 - DRYWELL ATMOSPHERIC COOLING Purpose The purpose ~ of this test is to verify the ability of the Drywell Atmosphere Cooling System to maintain design conditions in the drywell during operating conditions.
Description Drywell temperature is monitored to ensure design limits are .not exceeded. There are no changes for rerate which will affect the air flow distribution inside the drywell. The calculated increase in drywell temperature resulting from rerate is 2 F. Drywell temperatures are monitored in accordance with RT-O-4 0C-53 0-3, Drywell Temperature Monitoring, at approximately 95% power (original 100% power) and at rerated 100% power.
Level 1 Criteria Drywell temperature shall not exceed 145 F.
Level 2 Criteria Drywell temperature shall not exceed 140 F.
Results At approximately 95% and 100% power, drywell temperature data was collected. Calculations were performed to determine the drywell bulk average temperature at each of these conditions. Drywell bulk average temperature was 125 F at 95% power and 127.6*F at 100% power. All Level 1 and Level 2 acceptance criteria were satisfied.
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4 i k Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 51 of 55 STARTUP TEST 80 - THERMAL PERFORMANCE DATA COLLECTION Purpose The purpose of this procedure is to collect steady state data at.95%
rerated power (previous 100% power) at 100% rerated power and for an extended period of seven to nine days at full power following rerate implementation. This data is used to monitor operating thermal performance parameters at rerated power and to establish a baseline at the rerated power. There is no formal acceptance criteria for this test. The information collected is evaluated against historical performance data.
Descriotion Steady state data on thermal performance parameters is collected and evaluated at steady state conditions at 95% and 100%, and for an extended period at 100% rerate power. The test was performed in accordance with SP-2078, Thermal Performance Data Collection.
Level 1 Criteria l None.
Level 2 Criteria None. l l
Results Data was collected at approximate power levels of 95%, and 100% and for a period of nine days after attaining 100% power using SP-2078.
Comparisons were made with historical and predicted values. This data is the baseline for operation at rerated power. No acceptance criteria is associated with this test.
a < 'a s', Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 52 of 55 STARTUP TEST 81 - SURVEILLANCE TESTING Purcose The test verifies surveillance testing has been performed on all Tech Spec related instrumentation requiring recalibration as a result of power rerate changes.
Description Surveillance testing is performed on all Technical Specification (Tech Spec) related instrumentation requiring recalibration due to power ,
rerate changes (i.e. setpoint change, range change, etc.). This test '
contains signoffs for all of the required surveillance tests. A completed copy of this test documents that all the required surveillance testing is complete.
Level 1 Criteria None.
Level 2 Criteria None. )
Results All surveillance tests were completed prior to startup with the exception of SI3A-2-RPS-A through DFQ, Functional Test of RPS Card File.
This exception was documented by Test Exception Report 95-01. The card file functional was completed prior to the outage instead of during the outage. The card file functional was not effected by rerate even thouah administratively it was listed in the instrumentation list. All RPS instrumentation providing input to the card file was recalibrated. The card file functional frequency was changed from monthly to quarterly and therefore was not required to be performed during the outage. There was no effect on rerate requirements and no effect on the operation of the plant. This test exception is administrative only.
Rod Block Monitor 'A' and 'B' calibrations / functional checks were completed after startup prior to reaching 30% reactor power. All surveillance testing required for Tech Spec related instrumentation affected by power rerate changes was completed satisfactorily.
_ _ _ . . ~ _ _ _ . __ _ _ - . - _ . _ . . _ _ . _
aa. S
.a', Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report Page 53 of 55 l
1 STARTUP TEST 82 - STEADY STATE DATA COLLECTION Purcose j l
The purpose of this procedure is to collect steady state data during the plant startup following rerate implementation. A portion of this data 4 is used to project, using extrapolation techniques, operating
, performance parameters at rerated power levels before the previous power rating is exceeded. The balance of data collected is supplemental and may be used in evaluating the extrapolated parameters. The final set of data collected establishes the baseline for the rerated power.
I Descriotion l
l The first two data sets, taken at Test Conditions 2 and 3, include I baseline information (for extrapolation) to project . operating performance parameters at rerated conditions. Extrapolations of i specific important plant parameters will be made from each additional data set collected to project the rerated values at the subsequent test conditions. There is no formal acceptance criteria for this test. The information collected at each test condition will be evaluated against predicted performance values. Predicted values were determined using the data gained from the Unit 2 startup test program.
Data will be collected at approximately the following rerated power levels:
i TEST CONDITION ORIGINAL POWER RERATE POWER LEVEL RERATE MWT LEVEL (%)
I l 2 89.3% - 90.3% 85%-86% 2939 - 2974 1 l
3 94.5% - 95.6% 90%-91% 3112 - 3147 )
i 4 99.8% - 100.8% 95%-96% 3285 - 3320 ;
l 5 N/A 97%-98% 3354 - 3389 l 6 N/A 99%-100% 3423 - 3458 l
l Level 1 Criteria l
None.
Level 2 Criteria 4 None.
'l
.? . ? ;. 1 5 i'* Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report i Page 54 of 55 STARTUP TEST 82 - STEADY STATE DATA COLLECTION (Continued)
Results Data was_ recorded for over 160 plant parameters at Test Conditions 2 through 6. For the most part, the data recorded tracked very well with j the predicted and/or historical values. Based on the experience gained from Unit 2, procedures were revised prior to startup to set initial EHC pressure set to 940psig and allow a plus or minus 5 psig band of control during operation. With this new setting, reactor pressure was easily controlled at or just below the predicted 100% power value of 1035 psig.
Extrapolations were performed for various instruments recording first stage pressure, turbine inlet pressure, steam flow, feedwater inlet temperatures, and control valve positions. Pressures tracked consistently with the predicted values gained from Unit 2. Initially lowering pressure set to 940psig prevented the higher pressures found during the Unit 2 startup program.
)
Steam flow tracked very well with the predicted curve from Unit 2; however, the steam flow values typically tracked lower than anticipated.
Feedwater temperatures followed the predicted curves; however, the actual temperatures were 8*F to 10 lower than the curve. A review of historical data indicated feedwater temperatures to.be lower than the predicted values by about the same amount. The feedwater temperatures at each test condition almost match the historical and extrapolated values; therefore, there is no concern with this data. No action is required. '
With EHC Pressure Set at 940 psig plus or minus 5 psig, the control I valves opened to within about 1% of the predicted values. This good 1 response was due to a proper initial pressure set and a recalibration of the LVDT. l l
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,J'e Peach Bottom Atomic Power Station Unit 3 Rerate Startup Test Report l Page 55 of 55 1
This concludes the PBAPS Unit 2 Rerate Startup Test Report. )
l Prepared By w < < 'zu ,
'e'[ Ele 2 rt Test, Director 1 Reviewed By i V, U- MNb RerYteTaskMager -
Reviewed By ~ / em N h /1 4tWr7~4e#6 Senior ManageF Plant Engineering App' roved By Director of Site Engineering e
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