ML20078S950

PBAPS Cycle 11 Startup Rept for Unit 2

ML20078S950
Person / Time
Site:	Peach Bottom
Issue date:	12/16/1994
From:	Rainey G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9412290322
Download: ML20078S950 (64)

Text

. . _ . _ __-. . _ .-m . _ _ . _ _ _ _ . . _ _ _ _ . . _ . . _ _ - _ _

3 Gerald C. Rainey Vice eresident Peach Bottom Atomic Power Station 4

s 4 PECO ENERGY etw < ~ a--,

RD 1. Box 208 Delta. PA 17314-9739 4 717 456 7014 December 16, 1994 U.S. Nuclear Regulatory Commission s Attention: Document Control Desk i Mail Station P1-137 Washington, DC 20555

Subject:

Peach Bottom Atomic Power Station Unit No.

2 Report of Plant Startup Following The Tenth Refueling Outage Gentlemen:

Enclosed is the Peach Bottom Atomic Power Station Startup Report for Unit No. 2 Cycle 11. The report is submitted pursuant to reporting requirement 6.9.1.a in Appendix A to Facility Operating License No. DPR-44.

Sincerely, d ainey Vice President, Peach Bottom Atomic Power Station

[ i GRR/MDk/vta

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Enclosure cc: R.A. Burricelli, Public Service Electric & Gas R.R. Janati, Commomwealth of Pennsylvania W.L. Schmidt, USNRC Senior Resident Inspector, PBAPS ,

R.I. McLean, State of Maryland l T.T. Martin, Administrator, Region 1, USNRC.

H.C. Schwemm, Atlantic Electric A.F. Kirby, III, Delmarva Power INPO Records Center

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CYCLE 11 STARTUP REPORT i

UNIT 2

l SUBMITTED TO j THE U.S. NUCLEAR REGULATORY COMMISSION j PURSUANT TO FACILITY OPERATING LICENSE DPR-44 l

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! DECEMBER 1994 ,

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TABLE OF CONTENTS Executive Summary 1 1.0 Purpose 2 2.0 Program Description 2 3.0 Acceptance Criteria 4 4.0 Rerate Startup Test Program Summary 4 5.0 Chronology of Events 6-6.0 Test Results Summaries 14 STI-1 Chemical & Radiochemical 15 STI-2 Radiation Measurements 16 STI-4 Shutdown Margin 19 STI-5A CRD Insert / Withdraw Times 20 STI-5B CRD Scram Timing 21 STI-11 LPRM Calibration 23 STI-12 APRM Calibration 24 STI-14 RCIC 25 STI-15 HPCI 28 STI-18 Core Power Distribution 31 STI-19 Core Performance 32 STI-22 Pressure Regulator 34 '

STI-23A Feedwater Level Control 40 STI-25 Main Steam Isolation valves 43 STI-29 Recirc. Flow Control 46 STI-33 Turbine Stop Valve ST 48 STI-34 Turbine Control Valve ST 51 STI-35 Recirc. System Flow Calibration 54 3 STI-72 Drywell Atmospheric Cooling 55 l STI-80 Thermal Performance Test 56 i STI-81 I&C Surveillance Tests 57 l STI-82 Steady State Data Collection 58 TABLES and FIGURES l TABLE 1 - Tests Performed for Power Rerate 11 f FIGURE 1 - Rerate Power / Flow Map 12 l FIGURE 2 - RCIC Acceptance Curves 13 e 1 i

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 1 of 61 ,

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EXECUTIVE

SUMMARY

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This Startup Test Report is submitted to the Nuclear Regulatory '

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 2 following the implementation of Power Rerate during 1 the Fall 1994 Refueling Outage. Il The result of Power Rerate is an increase in reacto7: power equal to 5% of the original rated thermal power. All testing identified ,

within the PBAPS Updated Final Safety Analysis Report (UFSAR) l Chapter 13.5 was addressed and evaluated for applicability to this i

increased licenaed 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 20, 1994. The unit was (

synchronized to the grid on October 22"d, marking the official end to the Unit 2 loth refueling outage. The new rerated 100% power l (3458 MWt/1159 MWe) was first achieved on October 29, 1994. All ;

required Rerate Startup Tests were completed by November 7, 1994. '

Over 60 Rerate Startup Tests were performed satisfactorily during

, the startup. A total of twelve (12) Test Exception Reports (TERs) were initiated during the testing program. TERs document unexpected or unsatisfactory conditions encountered during testing. l All Test Exceptions were satisfactorily dispositioned. All further j l actions resulting from the TERs are being tracked as separate open i items.

. No adjustments were required to control systems for the following plant systems: EHC - Pressure Regulator, Feedwater, Recirculation, Reactor Core Isolation Cooling (RCIC), or High Pressure Coolant Injection (HPCI). All systems performed in a stable manner during

the plant suartup and during transient testing. The unit is

operating very well at rerated conditions.

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 2 of 61 1.0 Purpose l This Startup Test Report summarizes the testing performed on

Peach Bottom Atomic Power Station (PBAPS) Unit 2 following the

! implementation of Power Rerate. The result of Power Rerate is i an increase in reactor power equal to 5% of the original rated l 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 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.

l l 2.0 Program Description The power rerate startup testing requirements were developed 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 i

level. The testing was conducted following the 10* refueling l outage for Unit 2.

The majority of testing can be summarized into the following categories:

1) Verifyihg 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.

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).

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Peach Bottom Atomic Power Station l Unit 2 Rerate Startup Test Report l Page 3 of 61 l 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 i 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.

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Rerate i Test Condition Power Level Rerate MWT l 1 <85% <2939 i 2 85%-86% 2939 - 2974 l 3 90%-91% 3112 - 3147 l 4 95%-96% 3285 - 3320 5 97%-98% 3354 - 3388 6 99%-100% 3423 - 3458 i l I

All testing within a Test Plateau must be completed and t

approved by PORC (Plant Operations Review Committee) prior to

! increasing power to the subsequent Test Plateau. Rerate l 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%.

l l 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 2 Rerate Startup Test Report l Page 4 of 61 i 3.0 Acceptance Cr!.teria i 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.

Following resolution, applicable tests must be repeated to 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 satisfied, operating and testing plans would not necessarily be altered. Investigation of the measurements and the

, 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 l

" Startup on October 20, 1994 and ended with all required Rerate Startup Tests complete on November 7, 1994. The unit was l synchronized to the grid on October 22"d, marking the official end to the Unit 2 10th refueling outage. The new rerated 100%

power (3458 MWt) was first achieved on October 29, 1994.

In general, the unit operates very well at the rerated conditions. No adjustments were required to control systems i for the following: EHC - Pressure Regulator, Feedwater,

, Recirculation, Reactor Core Isolation Cooling (RCIC) , or High Pressure Coolant Injection (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. Adequate margin to the RCIC overspeed trip was demonstrated during the RCIC cold quick start at 100%

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power. Based on these results, the modification recommended by GE SIL 377 is not required. HPCI met all design and operability requirements; however, the second speed peak observed during the cold quick start exceeded the Level 2 acceptance criteria. Although the Level 2 criteria was not satisfied, approximately 8% margin remained to the overspeed trip. This is discussed further in the.results for STI-15D.

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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• 1 Peach Bottom Atomic Power Station' l Unit 2 Rerate Startup Test Report '

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-Page 5 of 61 4.0 'Rerate Startup Test Program Summary (Continued)

All Rerate Startup Tests were performed satisfactorily during the startup from 2R10 refueling outage. Table 1 identifies all of the required Rerate Startup Tests and the Test conditions in which each test was performed. A total of ,

twelve (12) Test Exception Reports (TERs) were initiated during the testing program. Two of.these TERs were cancelled by PORC because they documented mechanical problems noticed during testing which did not affect the performance of testing nor the ability of the system to perform its design function.

These items are being tracked through Action Requests. Brief descriptions of the remaining ten (10) test exceptions (TERs) and the respective resolutions follow. Further' discussion for each TER is found in the Results Section for the associated Startup Test.

1. One Level-1 Acceptance Criteria failure was documented.

RCIC failed to attain rated flow during the 150 psig test. The test was reperformed at a slightly higher reactor pressure with all criteria satisfied.

2. Two Level 2 Acceptance Criteria failures were observed:

a) CRD 38-43 had a fast withdraw time of approximately 4 inches per second (however, within the Design Basis Document (DBD) design stroke time). An Action Request was initiated to replace the directional control valves, b) HPCI Cold Quick Start second turbine. speed peak of 4700 rpm exceeded the criteria of 4305 rpm. An Action Request was initiated to investigate and resolve.

3. Three similar observations were made of a-drift within the pressure regulator bias potentiometer during the restoration from the pressure regulator failover testing. Testing was not affected. Troubleshooting

, determined the most probable cause to be in-the setpoint

! voltage circuit of the 'B' pressure regulator. An Action Request was initiated for board _ replacement, i

4. Two extrapolation steps during Turbine Stop Valve and Turbine Control Valve testing at Test Condition 5 were unable to be performed due to EHC Pressure Set being

lowered 10 psig during Test Condition 4. Scram margins i

were reviewed, and tests were satisfactorily performed at Test Condition 6 (100% power).

5. Two cases exist where some of the data collected-

, throughout the startup could not be used based on the plant configuration. This caused the specific data to be invalid or inaccurate. In both cases, the remaining data was analyzed and all criteria were satisfied.

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) Peach Bottom Atomic Power Station j Unit 2 Rerate Startup Test Report q Page 6 of 61 i

l 5.0 Chronology of Events Event Date/ Time I

t Mode Switch to Startup (Test Condition 1) Oct 20/0200 SP-2041 Feedwater Incremental Regulation. Oct 20/0300 SP-2040 Pressure Regulator Incremental Oct 20/0300 -

j Regulation l Shutdown Margin Demonstration - Cycle 11 Oct 20/0600 i

j SP-2016 RCIC Operability Oct 20/1700 Turbine Shell/ Chest Warming Oct 20/2000 i

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SP-2020 HPCI Operability Oct 21/0200 1

Raise EHC Pressure Set to 950 Psig Oct 21/1000 4

Drywell Inspection Oct 21/1200 ,

SP-2017 RCIC Quick Start & Stability Oct 21/1500 l t

j Pull Control Rods until 4 BPV's Open Oct 21/1900  !

t 0 Roll Main Turbine Oct 21/2000 SP-2021 HPCI Quick Start & Stability Oct 21/2100 l Synchronize to Generator Oct 21/0400 i

i Increase Load to >15% and Hold for 4 Hours Oct 22/0500 Turbine overspeed Trip Testing /Resynch Generator Oct 22/0900 Increased Power to 20% (Hold - high sulfates) Oct 22/1100 i ,

1 SP-2027 Pressure Regulator Stability Oct 22/1400 '

i Sulfate Concentration Reduced to < 17 ppb Oct 24/1000

) Increased Power to 25% Oct 24/1000 i

) SP-2025 Feedwater Stability Oct 24/1100 I

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Peach Bottom Atomic Power Station i Unit 2 Rerate Startup Test Report

,' Page 7 of 61 l 5.0 Chronology of Events (Continued)

! Event Date/ Time Increased Power to 29% Oct 24/1300 Rod Block Monitor Cal /Functionals Oct 24/1400 i

SP-2032 Rerate I&C Surveillance Testing Oct 24/1400

] Increased Power to 35% Oct 24/1500 f Control Rod Drive Scram Time Testing Oct 24/1900 l SP-2030 Thermal Performance Data Oct 25/0000 l

j APRM Calibration Oct 25/0800 i

, Increased Power to 60% Oct 26/0800 q Perform OD-1. Oct 26/1300 SP-2025 Feedwater Stability Oct 26/1400 SP-2027 Pressure Regulator Stability Oct 26/1600 Increased Power to 71% Oct 26/2000 l SP-2024 MSIV Individual Closures Oct 26/2100 i Increased Power to 75% Oct 26/2100 SP-2024 MSIV Individual Closures Oct 26/2200 l

CH-420 SJAE Off-Gas Sampling Oct 26/2300 i i

Increased Power to 80% Oct 26/2300 l SP-2025 Feedwater Stability .0ct 27/0100 l 1

Increased Power to 85% (Test Condition 2) Oct 27/0400 SP-2030 Thermal Performance Data Oct 27/0600 SP-2034 Steady State Data Collection Oct 27/0700 APRM Calibration Oct 27/0700 Feedwater Heater Level Controller Adjustments Oct 27/0800

Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 8 of 61 5.0 Chronology of Events (Continued)

Event Date/ Time Increased Power to 90% (Test Condition 3) Oct 27/0900 HP-C-200 Radiation Measurements Oct 27/1100 SP-2031 Thermal Limits Evaluation Oct 27/1100 SP-2034 Steady State Data Collection Oct 27/1200 APRM Calibration Oct 27/1200 SP-2029 Control Valve Surveillance Test Oct 27/1300 SP-2028 Stop Valve Surveillance Test Oct 27/1400 PORC Test Plateau A Results Oct 27/1600 Increased Power to 95% (Test Condition 4) Oct 27/2200 HP-C-200 Radiation Measurements Oct 28/0000 Drywell Temperature Monitoring Test Oct 28/0000 f

l SP-2030 Thermal Performance Data Oct 28/0100 l

APRM Calibration Oct 28/0100 SP-2033 Rerate Chemistry Oct 28/0200 l

SP-2031 Thermal Limits Evaluation Oct 28/0200 SP-2034 Steady State Data Collection Oct 28/0200 SP-2027 Pressure Regulator Stability Oct 28/0400 l SP-2029 Control Valve Surveillance Test Oct 28/0600 SP-2028 Stop Valve Surveillance Test Oct 28/0900 I PORC Test Plateau B Results Oct 28/1200 Lowered EHC Pressure Set to 940 Psig Oct 28/1600 l SP-2034 Steady State Data Collection Oct 28/1700 l

( Peach Bottom Atomic Power Station

! Unit 2 Rerate Startup Test Report l Page 9 of 61 5.0 Chronology of Events (Continued) i Event Date/ Time <

Increased Power to 97% (Test Condition 5) Oct 28/2300 HP-C-200 Radiation Measurements Oct 29/0000 APRM Calibration Oct 29/0000 SP-2031 Thermal Limits Evaluation Oct 29/0100 SP-2034 Steady State Data Collection Oct 29/0100 Feedwater Heater Level Controller Adjustments Oct 29/0200 SP-2025 Feedwater Stability Oct 29/0200 SP-2027 Pressure Regulator Stability Oct 29/0600 SP-2029 Control Valve Surveillance Test Oct 29/0800 SP-2028 Stop Valve Surveillance Test Oct 29/0900 PORC Test Plateau C Results Oct 29/1100 Increased Power to 100% (Test Condition 6) Oct 29/1200

, HP-C-200 Radiation Measurements Oct 29/1300 Drywell Temperature Monitoring Test Oct 29/1300 SP-2030 Thermal Performance Data Collection 7-9 Day Soak Oct 29/1300 APRM Calibration Oct 29/1400 SP-2034 Steady State Data Collection Oct 29/2000 SP-2033 Rerate Chemistry Oct 30/1500 ,

LPRM Gain Calibration Oct 30/1500 RE-27 TIP Reproducibility Oct 31/0300 Feedwater Heater Level Controller Adjustments Oct 31/0800 SP-2019 RCIC Cold Quick Start Oct 31/0800 SP-2018 RCIC Stability at Rerated Pressure Oct 31/0800 I

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report {

Page 10 of 61 l 1

5.0 Chronology of Events (Continued) l Event Date/ Time l SP-2031 Thermal Limits Evaluation Oct 31/1000 Core Flow Verification Oct 31/0800

. SP-2023 HPCI Cold Quick Start Oct 31/1600 SP-2022 HPCI Stability at Rerated Pressure Oct 31/1600 Recirc High Speed Stop Adjustments Nov 1/0800 Nov 1/0800 SP-2056 Containment Noise Monitoring SP-2029 Control Valve Surveillance Test Nov 3/0900 SP-2028 Stop Valve Surveillance Test Nov 3/1000 ,

Reduce Power to 80% Power /60% Flow for ARTS /MELLLA MAT 5374B Nov 5/0300 i

Partial MAT 5374B (Recirc Flow Steps) Nov 5/0600 Ramp Back to 100% Power /86% Flow Nov 5/0700 i

Partial MAT 5374B (Recirc Flow Steps) Nov 5/0600 l SP-2030 Thermal Performance Data Collection 7-9 Day Soak Complete Nov 7/0700 PORC Test Plateau D Results Nov 10/1000

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 11 of 61 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 SA CRD Insert / Withdraw Times X SB CRD Scram Timing X 11 LPRM Calibration X 12 APRM Calibration X X X X X X 14A RCIC (150#) X 14B RCIC (> 920#) X 14C RCIC Stability (Rerated X Pressure) 14D RCIC Cold Quick Start X i 15A HPCI (150#) X 15B HPCI (> 920#) X 15C HPCI Stability (Rerated X Pressure) 15D HPCI Cold Quick Start X l 18 Core Power Distribution X 19 Core Performance X X X X 22 Pressure Regulator' X X X l I 23A Feedwater Level Contro18 X X 25 Main Steam Isolation X valves 29 Recirc. Flow Control X 33 Turbine Stop Valve ST X X X X 34 Turbine Control Valve ST X X X X 35 Recirc. System Flow X l Calibration i 72 Drywell Atmospheric X X Cooling 80 Thermal Performance Test X X X X X X l 81 I&C Surveillance Testsi X 82 Steady State Data X X X X X Collection 1 Pressure Regulator stability checks are performed at approximate rerate power levels of 20%, 60%, 95%, and 97%

2 Levet setpoint changes are performed four times, once each at approximate rerste power levels of 25%, 60%,

80%, and 97%.

3 -These are to be performed prior to the plant condition for which the instrunent is required to be operable, t

Peach Bottom Atomic Power Station l Unit 2 Rerate Startup Test Report j Page 12 of 61 i

! FIGURE 1

! Rorate Power / Flow Map l

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Unit 2 Rerate Startup Test Report Page 13 of 61 FIGURE 2 l RCIC Acceptance Criteria Curves for Capacity and Actuation l

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4 Peach Bottom Atomic Power Station 1 Unit 2 Rerate Startup Test Report j Page 14 of 61 i

j 6.0 Test Results Summaries 1

l STARTUP TEST 1 - CHEMICAL AND RADIOCHEMICAL l Purpose l

4 The primary objective of this test is to maintain control of and 4

knowledge about the quality of the reactor coolant chemistry.

Descriotion d Chemical and radiochemical samples are taken in accordance with the l following plant procedures throughout power ascension to rerated

conditions. Specific criteria evaluation for rerated conditions is l performed in Special Procedure SP-2033 at the original 100% power level (Test Condition 4) and at the rerate 100% power level (Test Condition 6).

l ST-C-095-819-2 ST-C-095-823-2 ST-C-095-864-2 ST-C-095-857-2 ST-C-095-859-2 ST-C-095-822-2 ST-C-095-825-2 ST-C-095-820-2 In addition, normal plant chemistry sampling is performed in accordance with CH-10. A Flag File Report is run at 95% (original i

100%) and 100% rerate power which 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 are performed to obtain baseline data. There is no acceptance criteria specifically associated with these portions of the

! Chemistry testing.

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 25oc.

3. Primary Coolant chloride ion concentration is less than or i 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.

5. Site Tech Spec Dose Rate < 100%.

Level 2 Criteria None.

l Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 15 of 61 STARTUP TEST 1 - CHEMICAL AND RADIOCHEMICAL (Continued)

Results Special Procedure SP-2033, Chemistry Rerate Information, was 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 Actual Data Actual Data Acceptance Parameter (95%) (100%) Criteria Primary Reactor Coolant Iodine 1. 4 94 x10 -4 1.575x10-4 s 0.2gCI/gm Primary Reactor Coolant s 5.0 Conductivity 0.150 0.103 ymhos/cm Chloride Ion l Concentration 1.4 3.6 s 200 ppb i Noble Gas s 320,000 Release Rate 1151.9 1054 pCi/sec i

Noble Gas Dose Rate < 30% < 30% < 100% l l

l l l A Flag File Report was run at 95% and 100% rerate power which summarized the chemistry data obtained, compared the values to plant requirements I and flagged any parameters which exceeded their specific limit. Various minor items were identified on the Flag File as exceeding their given limits. All of these items were addressed and resolved within the test procedures. The majority of these items required no actions to be taken except for the following two items. Reactor Water Cleanup (RWCU)

Influent Sulfates were high. The sulfates were due to contaminants following the 2R10 refueling outage. Plant sampling procedure, CH-10, required an action plan to be developed at 95% power. The action plan was in progress during the 100% power test. This was expected since the unit was in a hold condition (maintaining reactor power less than 20%)

early in the startup due to high sulfates. Off-Gas System Hold-Up Pipe Flow was high at both power levels due to an unidentified condenser leak. A leak search is in progress by the System Manager and Operations.

Carryover was not able to be determined at either 95% or 100% power l

since I-131 was not detected in the reactor water or condensate influent samples. In general, chemistry has not shown any significant changes due to power rerate.

l Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report ,

Page 16 of 61 STARTUP TEST 2 - RADIATION MEASUREMENTS Purnose 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.

Description Radiation levels are measured at various locations in the plant at 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 None.

l Results

' Radiation surveys were conducted at rerated power levels of 90%, 95%,

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 (HPCI), and Residual Heat Removal (RHR) system runs. These results are l shown in Tables 2.2 and 2.3, respectively.

i Essentially, the dose rates are the same as those experienced at the original ?00% power. The Main Turbine Deck is the only area er eriencil.[ increased dose rates. No area postings were changed as a resalt 'd achieving the rerate 100% power level.

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l Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 17 of 61 STARTUP TEST 2 - RADIATION MEASUREMENTS (Continued) 1 l

1 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 0.4 0.4 0.2 0.4 Outside B SJAE 0.8 0.6 0.6 0.6 Outside Mech Vac Pp Rm 0.4 0.2 0.5 0.2 Moisture Separator Area 430 500 500 500 4A FW Heater Room 10 10 12 12 4B FW Heater Room 32 42 45 40 4C FW Heater Room 12 12 14 15 TB Fan Room -El 195 0.4 0.2 0.3 0.3 A RFPT Room 60 60 70 70 B RFPT Room 60 60 60 60 C RFPT Room 50 50 60 60 SA FW Heater Room 120* 34 50 60 SB FW Heater Room 110 2 35 44 50 5C FW Heater Room 100 1 28 42 45 TB El 165 General Area 0.3 0.3 0.3 0.3 Turbine Deck 90 100 140 150 Outside - Fence Area 0.2 0.1 0.3 0.3 Drywell Equip. Hatch Door 1.4 2.5 2.2 2.0 TIP Room Door 0.4 0.1 0.7 0.5 Drywell Personnel Airlock 40 30 32 32 1

1 - Location of these readings was corrected by HP to reflect the actual area which would be accessed by personnel with the unit at power.

Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 18 of 61 STARTUP TEST 2 - RADIATION MEASUREMENTS (Continued)

TABLE 2.2 Radiation Surveys During RCIC and HPCI System Runs Plant Location Rerate Power Level = 100%

RCIC System Run HPCI System Run RCIC Room 6-120 mrem /hr NA HPCI Room NA 5-110 mrem /hr '

Torus Room 80-120 mrem /hr 300-400 mrem /hr North Isolation Valve Room NA 5-500 mrem /hr South Isolation Valve Room NA 2-4 mrem /hr TABLE 2.3 Radiation Surveys During RHR System Runs Plant Location Rerate Power Level = 100%

2A RER Room 12-20 mrem /hr 2B RHR Room 6-12 mrem /hr 2C RHR Room 16-26 mrem /hr 2D RHR Room 15-25 mrem /hr

Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 19 of 61 STARTUP TEST 4 - SHUTDOWN MARGIN Purcose 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.

Descriotion l

Shutdown margin demonstration is performed in accordance with ST-R-002-910-2, Shutdown Margin, during Test Condition 1.

Level 1 Criteria shutdown margin is 20.38% (delta K) /K + R.

Level 2 Criteria None.

1 Results For Unit 2 Cycle 11, the required shutdown margin must be greater than 0.38% (delta K)/K + R, where R is equal to 0.410% (delta K) /K.

Therefore, the calculated shutdown margin for Cycle 11 must be greater than 0.790% (delta K)/K.

As Unit 2 reached criticality, data was collected to calculate Shutdown Margin in accordance with ST-R-002-910-2, Shutdown Margin (Unit 2 -

Cycle 11). Cycle 11 shutdown margin was determined to be 1.584%

(delta K) /K. This satisfies the Level 1 Acceptance Criteria.

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1 Peach Bottom Atomic Power Station j Unit 2 Rerate Startup Test Report j Page 20 of 61 STARTUP TEST 5A - CONTROL ROD DRIVES - Insert / Withdraw Timing

l Purpose j

I This testing demonstrates that the control rods meet Technical i specification requirements for RPIS full in, RPIS full out, and i uncoupling checks.

1 Description i

! Control rod insert / withdraw timing is conducted during Test Condition 1 j in accordance with ST-O-003-465-2, Control Rod Withdraw Tests.

4 j Level 1 Criteria i

j RPIS Full in, RPIS Full out, and uncoupling checks are completed i satisfactory for all control rods.  !

Level 2 Criteria i

Insert and withdraw stroke times correlate to 3 inches per second or one 4 position per second.

l l Results I All control rods were stroked in accordance with ST-O-003-465-2. Level i 1 Acceptance Criteria was satisfied for all control rods. Control Rod j

' 38-43 had a withdraw time of approximately 4 inches per second which exceeds the Level 2 Acceptance criteria.  :

J Test Exception Report #1 documents this criteria failure. The Control Rod Drive (CRD) Design Basis Document (DBD) gives the acceptable rod speed as 3-5 seconds. An indication of excessive rod speed is double notching. No double notching has been observed for rod 38-43. Based on this information, the resolution to this exception is to allow the rod i

j to operate in this condition until its scheduled PM when the directional i i control valves will be replaced. If double notching is experienced, I j then the directional control valves will be replaced as soon as  ;

possible.

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i Peach Bottom Atomic Power Station j Unit 2 Rerate Startup Test Report Page 21 of 61 i

! STARTUP TEST 5B - CONTROL ROD DRIVES - Scram Timing Purpose

This testing demonstrates that the control rods meet Technical

Specification requirements for scram times.

I j Description

Scram timing of control rods is performed during Test Condition 1 in j accordance with ST-R-003-460-2, CRD Scram Insertion Timing, Full In and i Full Out Position Indication Check, and Rod Coupling Integrity Check For

] All Operable Control Rods.

l Level 1 Criteria t

l 1. The total average 5% scram time is less than or equal to 0.375 I seconds.

2. The total average 20% scram time is less than or equal to 0.90 i seconds.

3. The total average 50% scram time is less than or equal to 2.0 i seconds.

4. The total average 90% scram time is less than or equal to 3.5 '

j seconds.

! 5. The average 5% scram insertion times for the three fastest control i i rods of all groups of four control rods in a two by two array is i j less than or equal to 0.398 seconds. I

6. The average 20% 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 0.954 seconds.

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7. The average 50% scram insertion times for the three fastest control l l rods of all groups of four control rods in a two by two array is l

less than or equal to 2.120 seconds.

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! 8. The average 90% scram insertion times for the three fastest control I

rods of all groups of four control rods in a two by two array is j less than or equal to 3.8 seconds.

4 Level 2 Criteria

None.

Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 22 of 61 i

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 SB.1. 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 i shown below with the test results.

TABLE SB.1 CRD Scram Timing Results Acceptance Test Scram Time Description Criteria Results (Seconds) (Seconds)

Total Average 5% scram time s 0.359 0.333 Total Average 20% scram time s 0.92 0.722 Total Average 50% scram time s 1.99 1.459 Total Average 90% scram time s 3.67 2.578 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 0.374 Average 20% scram insertion times for the three fastest control rods of all groups of 4

four control rods in a two by two array s 0.974 0.793 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 1.574 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 2.714

i Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 23 of 61 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-230-2, 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  ?

I operable LPRMs were successfully calibrated. All operable LPRM raw readings were within 2 absolute value points of the last P-1 Calibrated 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.

Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 24 of 61 STARTUP TEST 12 - APRM CALIBRATION l

Purpose The purpose of this test is to calibrate the average power range monitors (APRMs).

Description Each APRM channel reading is adjusted to be consistent with the core thermal power as determined from the heat balance. This calibration is performed as necessary during power ascension in accordance with )

ST-O-60A-210-2, APRM System Calibration During Two Loop Operation, or i RT-R-60A-210-2, APRM Gain Adjustment.

Level 1 Criteria APRMs are correctly set to calculated APRM setting.

Level 2 Criteria None.

Results l APRM Calibrations or Gain Adjustments were performed during each Test Condition (1 through 6) during the Rerate Startup Test Program to ensure the following:

1. The APRMs were correctly set to the calculated j APRM setting.

1

2. The corresponding APRM gain adjustment factors (AGAF) values on the P-1 or OD-3 edit are s 1.00.

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Each performance of ST-O-60A-210-2, APRM System Calibration During Two Loop Operation, and RT-R-60A-210-2, APRM Gain Adjustment, was completed satisfactorily. No problems were encountered during these tests.

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! Peach Bottom Atomic Power Station

( Unit 2 Rerate Startup Test Report l Page 25 of 61 l

l STARTUP TEST 14 - REACTOR CORE ISOLATION COOLING SYSTEM i

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 four subtests (Startup Test Instructions, STI-14A, -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.

Description STI-14A At 150 Psig, as part of the normal plant startup, ST-O-013-200-2, RCIC Flow Rate at 150 Psig, Alternate Control Panel Test, and Remote Shutdown Panel Test, is performed in conjunction with Special Procedure SP-2016 to demonstrate adequate control of the turbine and rated flow capability.

STI-14B l Using the current controller settings, RCIC is operated in the CST to l

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 is performed '

using ST-0-013-301-2, RCIC Pump, Valve, Flow and Unit Cooler Functional and In-Service Test, and Special Procedure SP-2017. A stability check of the RCIC system is also performed during this test by introducing small flow steps following the system quick start.

STI-14C System stability at rerated operating pressure shall be demonstrated by introducing small step disturbances in flow demand in accordance with RT-X-013-230-2 and Special Procedure SP-2018.

STI-14D A cold quick start is performed in accordance with RT-O-013-725-2, RCIC Response Time Test and Special Procedure SP-2019 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.

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l Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 26 of 61 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) i

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.

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3. Turbine gland seal condenser system shall be capable of preventing steam leakage to the atmosphere.

Results STI-14A With reactor pressure at approximately 163 psig, the RCIC system was started. During a 3 minute, 41 second run, RCIC achieved a flow rate of only 420 gallons per minute (gpm). This fell short of the system's rated flow rate of 600 gallons per minute. This violated a Level 1 acceptance criterion. Shift Management was notified of the Level 1 criteria violation, and testing was put on hold. The Plant Manager was notified of the failure and hold condition. Test Exception Report (TER)

1. 4 was generated to document this f ailure. PORC was convened to discuss a proposed resolution.

! PORC Position No. 24 discusses the 150 psig reactor pressure value l associated with RCIC operability testing. 150 psig is the lowest l setpoint for EHC pressure regulator. The PORC Position establishes 175 I

psig as a reasonable value of reactor pressure by which RCIC operability must be determined based on uncertainties in the EHC pressure setpoint and reactor pressure indications. Based on PORC Position 24 and the fact that reactor pressure only indicated 163 psig during the initial RCIC run, the resolution was to use reactor pressure, as indicated on the Plant Monitoring System (PMS) computer, to verify pressure less than 175 psig, increase EHC pressure set slightly, and reperform the test.

.- - .-----. .- - - . _- - = . -- ..

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l Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 27 of 61 i

STARTUP TEST 14 - RCIC SYSTEM (Continued)

Results (Continued)

STI-14A (Continued)

PORC agreed with this resolution, and the Plant Manager released the i

HOLD Condition contingent upon the successful performance of the test.

EHC pressure set was increased to 170 psig (reactor pressure indicated 174 psig), and the test was reperformed. Rated RCIC flow was achieved.

All acceptance criteria were satisfied. TER #4 was closed.

STI-14B With reactor pressure at approximately 948 psig, RCIC system stability was verified by introducing a 60 gpm negative flow step followed by a 60 gpm positive flow step. Plots of the step inputs showed good system response. No controller adjustments were required. Following the stability check, RCIC was shut down, and a quick start was performed.

RCIC achieved rated flow of 600 gpm in 17.65 seconds with a pump discharge pressure of 1040 psig. All Level 1 and Level 2 acceptance criteria were satisfied.

i STI-14C and STI-14D At approximately 99.5% rerated reactor power and 1032 psig reactor pressure, a RCIC cold quick start was initiated. Rated flow (600 gpm) was attained in 17.9 seconds with a pump discharge pressure of 1180 psig. Peak RCIC turbine speed during the quick start was 4650 rpm. All l Level 1 and Level 2 acceptance criteria were satisfied. Based on the l 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. Small disturbances in turbine speed were input to verify adequate turbine response. Flow demand changes were performed to verify satisfactory flow control stability. RCIC responded very well to these disturbances. Successive peaks did not exist following the disturbances; therefore, decay ratios were zero. No adjustments were necessary. All Level 1 and Level 2 acceptance criteria were satisfied.

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 28 of 61 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 provide baseline data for future surveillance testing. This testing is separated into four subtests (Startup Test Instructions, STI-15A, -15B,

-15C, and -15D).

Descriotion STI-15A At 150 psig, as part of the normal plant startup, ST-O-023-200-2, HPCI Flow Rate at 150 Psig Steam Pressure, is performed in conjunction with Special Procedure SP-2020 to demonstrate adequete control of the turbine and rated flow capability.

SII-15B '

Uning 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-023-301-2, HPCI Pump, Valve, Flow and Unit Cooler Functional and In-Service Test and Special Procedure SP-2021. A stability check of the HPCI system is also performed by introducing small flow steps following the system quick start.

STI-15C i

system stability at rerated operating pressure shall be demonstrated by introducing small step disturbances in flow demand in accordance with RT-X-023-210-2 and Special Procedure SP-2022.

STI-15D A cold quick start is performed in accordance with RT-0-023-725-2, HPCI Response Time Test and Special Procedure SP-2023 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.

. - . . _ = - . - - _ . . . - .- .

Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report )

Page 29 of 61 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.

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 t

0.25.

l 3. Turbine gland seal condenser system shall be capable of preventing steam leakage to the atmosphere.

Results STI-15A The HPCI system was started with a reactor pressure of 164 psig. A flow rate of 3300 gpm was achieved in over 33 seconds.

This did not meet the acceptance criteria of attaining system rated flow (5000 gpm) within 30 seconds. This test is performed with the system flow returning to the Condensate Storage Tank (CST). In order to simulate a vessel injection, the HPCI Full Flow Test valve (MO-2-23-021)' is throttled to obtain the desired flow and pressure. This is a manual action which can not always be accomplished within the 30 second criteria. The test procedure allows the system to be shut down with the HPCI Full Flow Test valve in

the throttled position once the desired flow and pressure are met. The l quick start is then reperformed.

l l HPCI was shut down with the Full Flow Test valve left in a throttled position. The quick start was then reperformed. Within 18.2 seconds, rated flow of 5000 gpm was attained with a pump discharge pressure of 360 psig, satisfying all acceptance criteria.

STI-15'8 With reactor pressure at approximately 959 psig, HPCI system stability l

' was verified by introducing a 500 gpm negative flow step followed by a 500 gpm positive flow step. Plots of the step inputs showed good system response. No controller adjustments were required. Following the stability check, HPCI was shut down, and a quick start was performed.

HPCI achieved rated flow of 5000 gpm in 21.7 seconds with a pump discharge pressure of 1080 psig. The transient start first turbine speed peak was 937.5 rpm. The second and only subsequent speed peak was 4237.5 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 l satisfied.

Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 30 of 61 STARTUP TEST 15 - HIGH PRESSURE COOLANT INJECTION SYSTEM (Continued)

Results (Continued)

STI-15C and STI-15D At approximately 99.8% rerated reactor power and 1033 psig reactor pressure, a HPCI cold quick start was initiated. Rated flow (5000 gpm) was attained in 24.77 seconds with a pump discharge pressure of 1270 psig. The initial peak HPCI turbine speed during the quick start was 3000 rpm. The second speed peak was 4700 rpm, followed by the third and final speed peak of 4300 rpm. The first and third speed peaks satisfied their respective acceptance criteria requirements of being less than or equal to 4385 rpm and 4305 rpm. However, the second speed peak exceeded the required 4305 rpm, thus failing a Level 2 acceptance criteria. Test Exception Report (TER) #10 documents this criteria failure. An Action Request has been initiated to adjust the stop valve limit switch and to further investigate this problem, as necessary. HPCI achieved rated flow in less than 30 seconds with acceptable pump discharge pressure; therefore, there are no operability concerns. In addition, the system responded very well during the rated pressure stability test performed immediately following the cold quick start. All other acceptance criteria were satisfied.

Immediately following the cold quick start at rated conditions, HPCI system stability was checked. Small disturbances in turbine speed were  :

input to verify adequate turbine response. Flow demand changes were performed to verify satisfactory flow control stability. HPCI responded '

very well to these disturbances. Successive peaks did not exist following the disturbances; therefore, decay ratios were zero. No adjustments were necessary. All Level 1 and Level 2 acceptance criteria were satisfied.

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! Peach Bottom Atomic Power Station (

Unit 2 Rerate Startup Test Report I

! Page 31 of 61 1

I STARTUP TEST 18 - CORE POWER DISTRIBUTION l I

l

Purpose This test confirms both the reproducibility of the traversing incore l probe system (TIPS) readings and core power distribution symmetry. l l Description l This test is performed at Test Condition 6 in accordance with RE 27 -

1

Core Power Symmetry and TIP Reproducibility, and FM-UG-412, Analysis of 1 1 Total TIP Uncertainty Using NSTIP.

1 Level 1 Criteria i

j None.

i j Level 2 Criteria

1. The Total TIP uncertainty is < 7.1%.

} 2. The TIP traces shall be reproducible within 3.5% relative error.

i Results

! At approximately 99.8% power, reactor power distribution data was i

collected by repeatedly traversing the core axially with gamma TIPS. The data was subsequently processed by the Plant Monitoring System computer programs and 3D Monicore and trancmitted to the Fuel & Services Division i

for analysis. Results of the analysis determined the maximum total TIP uncertainty to be 1.51% 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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Unit 2 Rerate Startup Test Report Page 32 of 61 i

STARTUP TEST 19 - CORE PERFORMANCE

- Purpose e

This test evaluates the core performance parameters to assure plant thermal limits are maintained during the ascension to rerate conditions.

Descriotion As power is increased along a constant rod pattern line, core thermal power will be measured near 90% rerated power (Test Condition 3) and at each increment (approximately 3%) up to 100% rerate power (Test Condition 6), using the current plant methods of monitoring reactor power.

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 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 Critical Power)

3. Maximum MAPRAT (Core Maximum Average Planar Ratio)

4. FLLLP (Fraction of Percent Load Line Power (PCTLLP) to MELLLA Line)

Level 2 Criteria None.

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 33 of 61 STARTUP TEST 19 - CC."M PERFORMANCE (Continued)

Results i

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 91%, 95%, 97%, and l 100%. The results at each test condition are shown in Table 19.1. All acceptance criteria were satisfied.

a TABLE 19.1 Core Performance - Thermal Limits Evaluation Results Rerate Power Level Thermal Limit 91% 95% 97% 100%

MFLCPR s 1.000 0.903 0.941 0.926 0.947 MFLPD s 1.000 0.875 0.877 0.824 0.822 MAPRAT s 1.000 0.902 0.948 0.874 0.886 l

FLLLP s 1.000 0.852 0.872 0.873 0.875 l

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 34 of 61 STARTUP TEST 22 - PRESSURE REGULATOR Purcose 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 affected parameters are within acceptable limits during pressure induced transient maneuvers.

Descriotion l At approximate power levels of 20%, 60%, 95%, and 97% (Test Conditions 1, 4, 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 l 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-2027.

Total steam flow and pressure regulator output data is taken in l t

increments of 2% power during the power ascension to 100% rerate power. l The variation in the slope of the curve plotted on linear graph paper '

(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-2040.

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report j Page 35 of 61 STARTUP TEST 22 - PRESSURE REGULATOR (Continued) )

Level 1 Criteria i

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.

(This criterion does not apply to tests involving simulated f ailure of one regulator with the backup regulator taking over.)

2. The pressure response time from initiation of pressure setpoint change to the turbine inlet pressure peak shall be s 10 seconds.

3. Pressure control system deadband, delay, etc., shall be small enough that steady state limit cycles (if any) shall produce steam 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 l range) shall meet the following:

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% of Steam Flow Obtained With Valves Wide Ooen Variation 0 to 85% s 4:1

85% to 97% s 2

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85% to 99% 1 5:1 Results l Pressure Regulator Stability Pressure Regulator Stability testing was performed at rerate power l levels of 19%, 60%, 95%, and 96.5%. The data obtained during each test condition is summarized in Tables 22.1 and 22.2. The system response to l all size step changes at each power level was excellent. There were no l signs of divergence or oscillations. Decay ratios were zero for all step changes. Pressure response time and margins to scram setpoints l were satisfactory in all cases. No limit cycles were observed. All l Level 1 and Level 2 acceptance criteria applicable to the stability

testing were satisfied.

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 36 of 61 1

STARTUP TEST 22 - PRESSURE REGULATOR (Continued) 1- Results (Continued)

Pressure Regulator Stability 1 Pressure Regulator failovers were performed at rerate power levels of ,

19%, 60%, 95%, and 96.3%. The data obtained during each test condition  :

is summarized in Tables 22.3 and 22.4. In all cases, the backup I

pressure regulator took control when the controlling regulator was

, failed. All acceptance criteria were satisfied. Test Exception Reports

{

4 (TERs) #5, #6, and #7 document a drift within the regulator bias 4

potentiometer identified during the failover portion of the Pressure Regulator Stability test.

The drift occurs when the regulators are restored after being failed.

The drift is relatively small and has a minimal affect on the system operation. The pressure regulators are able to control pressure.

Throughout testing, the EHC and Pressure Regulator system has shown no signs of oscillations or divergence. Troubleshooting during power ascension has determined the most probable cause of the drifting to be in the setpoint voltage circuit of the 'B' pressure regulator. An Action Request has been generated for board replacement. GE concurred with this determination.

Pressure Regulator Incremental Regulation Determination Pressure Regulator Controller Output and steam flow data was collected approximately every 2% power during power ascension in accordance with Special Procedure SP-2040. This data was used to calculate the pressure regulator incremental regulation. Test Exception Report (TER) #12 explains why some of the data obtained could not be used in the incremental regulation calculation. At low power, controller output data was not valid due to the Bypass Valve Jack being used to control  ;

pressure / steam flow. Also, below 20% power, the regulators swapped back ~

and forth. Some of the data collected was indicative of'the backup regulator. At 20% power, the bias between the two regulators was set for 3 psi (in conjunction with SP-2027) with the 'A' regulator in control. All data af ter this point was valid. Calculations showed that the variation in incremental regulation satisfied the acceptance criteria for each steam flow range.

Follow.ing the completion of this test, it was identified that the 100%

value for Pressure Regulator Output was -1.43 volts versus the value of i

-1.5 volts listed in Data Sheet 2 of SP-2040. During the EHC alignment l just prior to startup, gains in the system were changed which resulted in the change in the 100% Pressure Regulator Output signal. Using the ,

same data as in the original incremental regulation calculations, all l calculations were reperformed utilizing a computer spreadsheet. All acceptance criteria were satisfied. The final results from the l spreadsheet calculation are shown in Table 22.5

Peach Bottom Atomic Power Station l Unit 2 Rerate Startup Test Report

Page 37 of 61

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STARTUP TEST 22 - PRESSURE REGULATOR (Continued) l TABLE 22.1

'A' PRESSURE REGULATOR STEP CHANGE DATA 4 Rerate Step Peak Pressure Peak Steady-

[ Power Size Pressure Response Power State Level (+/-) (psig) Time (%) Cycles

) -3 953.75 4.2 17.2 0

+3 957.5 4.8 20.28 0 i

2

-5 950.0 4.4 15.6 0 1

+5 961.25 5.12 20.28 0 19%

-10 947 3.5 15.6 0

+10 961.25 4.36 21.84 0

-3 980 2.0 60.0 0 1 +3 990.5 2.0 62.5 0

-5 980 2.5 55.0 0 j

+5 992 2.0 62.5 0 60%

-9 975 2.5 53.5 0 4 +9 986 3.0 62.5 0

-3 1026 5.0 97.5 0 1 +3 1034 3.0 99.0 0

-5 1024 3.0 96.0 0 3

95% +5 1034 3.5 99.0 0

-9 1020 4.5 99.5 0

+9 1035 5.0 99.0 0

] -3 1025 0.5 100 0 l +3 1026.5 2.5 100 0 i -5 1013 5.5 97.0 0 96.3% +5 1026.5 5.5 100 0

-8 1013 5.0 97.0 0

+8 1026.5 6.0 102 0 4

Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 38 of 61 STARTUP TEST 22 - PRESSURE REGULATOR (Continued)

TABLE 22.2

'B' PRESSURE REGULATOR STEP CHANGE DATA Rerate Step Peak Pressure Peak Steady Power Size Pressure Response Power State Level (+/-) (psig) Time (%) Cycles

-3 953.75 3.6 17.16 0

+3 961.25 5.32 20.28 0

-5 950.0 4.16 15.6 0

+5 961.25 4.2 20.28 0 19%

-10 946.25 4.36 15.6 0

+10 961.25 5.0 21.84 0

-3 983 3.5 56.5 0

+3 986 3.5 59.5 0 I 1

~

60%

+5 986 3.0 59.5 0

-9 977 3.0 55.0 0 )

+9 986 2.5 61.0 0

-3 1027 4.0 96.0 0 l

l

+3 1035 6.0 99.0 0 '

-5 1025 3.5 97.5 0 95% +5 1034 3.0 99.0 0

-8 1022 3.5 96.0 0

+8 1035 5.0 100.5 0

-1 1022 5.0 98.0 0

+3 1029.5 4.0 100 0

-5 1022 4.0 96.0 0 96.3% +5 1031 4.0 100 0

-8 1019 4.0 98.0 0

+8 1029.5 4.0 101 0

Peach Bottom Atomic Power Station ,

Unit 2 Rerate Startup Test Report l Page 39 of 61 l STARTUP TEST 22 - PRESSURE REGULATOR (Continued)

TABLE 22.3 Pressure Regulator 'B' Failed PRESSURE REGULATOR FAILOVER DATA Rerate Step Peak Pressure Peak Steady Power Size Pressure Response Power State Level (psi) (psig) Time (%) Cycles 19% 3 965 3.04 23.4 0 60% 3 992 3.0 64.0 0 95% 3 1040 2.0 102 0 96.3% 3 1035.5 4.0 103 0 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 19% 3 961.25 1.44 21.84 0 60% 3 986 1.0 61 0 95% 1 1032 0.5 94.5 0 96.3% 3 1031 2.0 101.5 0 l

i TABLE 22.5 Incremental Regulation Determination (Spreadsheet Calculation)

Steam Flow Incremental Regulation Variation Level 2 l Range Max / Min Criteria i Maximum Minimum l 0% to 85% 2.45 0.61 4.00 s 4:1 1

85% to 97% 0.91 0.65 1.39 s 2:1 85% to 99% 0.91 0.65 1.39 s 5:1 l

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report s Page 40 of 61 STARTUP TEST 23 - FEEDWATER SYSTEM - Water Level Setpoint Changes Purcose i

This test verifies that the feedwater system has been adjusted to provide acceptable reactor water level control at rerated conditions.

Description j

j During the 2R10 outage, speed regulation tests are performed on the A, B, and C reactor feedwater pumps in accordance with RT-B-06D-201-2, RT-B-06D-202-2, and RT-B-06D-203-2 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-006-230-2, Feedwater Control System Stability Response Test, and Special Procedure SP-2025. Level setpoint changes are performed at four power levels with the pump configurations listed below. At 25% power, only positive level setpoint steps will be performed.

Pumps Approximate Test i Operatino Rerate Power Condition 1 25% 1 2 60% 1 3 80% 1 3 97% 5 Total feedwater flow and Master Level Controller output data is taken in 3% to 5% increments to 100% rerate power. The variation in the slope of the curve plotted on linear graph paper (feedwater controller output versus total feedwater flow) must show that the incremental regulation is within the criteria.

Level 1 Criteria The transient response of any level control system related variable to l 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.

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l Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 41 of 61 l

STARTUP TEST 23 - FEEDWATER - Water Level Setpoint Changes (Continued) l l Level 2 Criteria (Continued) l

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") j does not exceed a factor of 2 to 1. 4

4. The turbine speed regulation variation between the three feedpumps l must match within 6% of rated speed. )

Results l

Speed Regulation l

Speed regulation tests were performed on the A, B, and C reactor l feedwater pumps during the 2R10 outage. The results of these tests are shown in Table 23.1. 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 1.0%. All acceptance criteria were satisfied.

TABLE 23.1 Reactor Feedwater Pump Turbine Speed Regulation RT-B-06D-201-2 RT-B-06D-202-2 RT-B-06D-203-2 RFPT A RFPT B RFPT C RFPT j

% 5.9 5.7 5.9 RPM /In. 63.40 61.23 64.29 l

Feedwater Stability Feedwater Stability testing was conducted at rerate power levels of 25%,

60%, 79.8%, and 96.6%. Six inch level setpoint changes were input and system response was monitored. At 25% power, only positive step changes j were performed in Single Element control. System response was satisfactory. At all other power levels, these disturbances were l initiated with Feedwater in 3-Element control initially, then steps were l reperformed with feedwater in Single Element Control. System response was not oscillatory and showed no signs of divergence. No system adjustments were required. All acceptance criteria related to system stability were satisfied.

a 1 4

l Peach Bottom Atomic Power Station j Unit 2 Rerate Startup Test Report Page 42 of 61

! STARTUP TEST 23 - FEEDWATER - Water Level Setpoint Changes (Continued) j Results (Continued)

Feedwater Stability f

} The level error between single and three element level control was

$ verified following the stability testing at 60%, 79.8%, and 96.6% power

} levels. At steady state conditions, reactor water level was monitored j as the Feedwater Level Control System was swapped from single element

control to three element control and back to single element control.

1 There was no noticeable change in reactor water level; therefore, no adjustments to the mismatch gain were necessary. The acceptance j criteria was satisfied.

Feedwater Incremental Regulation Determination j Feedwater controller output and feedwater flow data was collected approximately every 3-5% power during power ascension in accordance with l Special Procedure SP-2041. This data was used to calculate the j feedwater incremental regulation. Test Exception Report (TER) #11 i

explains why some of the data obtained could not be used in the I i incremental regulation calculation. Data taken with the minimum flow I

! valves open is not accurate since the feedwater pump recirculation flow )

I is not measured. Data taken when the pump discharge valve is throttled  !

is not representative of normal system values since the system j  !

resistance is higher resulting in a higher control signal value. The l remaining data was used to calculate the incremental regulation for l l normal operating configurations with 2 feedpumps running and with 3 l i

feedpumps running. The variation in incremental regulation for both of these conditions satisfied the acceptance criteria.

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 43 of 61 STARTUP TEST 25 - MAIN STEAM ISOLATION VALVES Purcoss This test functionally checks each MSIV for proper operation and measures each valve's closure time. This test also demonstrates that closure of an MSIV at the normal surveillance test power level (s75%)

will not cause a reactor scram at rerate conditions.

Descriotion l

Individual fast closure of each MSIV is performed in accordance with ST-O-07G-470-2, Main Steam Isolation Valve Closure Timing and Continuity l Test, and Special Procedure SP-2024, near the original 75% reactor power l level (approximately 71.4% rerate) to verify adequate scram margins. If l adequate scram margins exist, the test is repeated at 75% rerate power.

Level 1 Criteria

1. MSIV stroke time shall be between 3 and 5 seconds.

l Level 2 Criteria l 1. Reactor pressure must be 20 psi below scram. I (Peak pressure s 1065 psig) l

)

i

2. Neutron flux must be 10% below scram. I (Peak power s 109.96% during 71.7% power test) )

l (Peak power s 110.1% during 74% power test) l l

3. Steam flow in individual lines must be below the trip setpoint. '

l (Peak steam flow s 123.3 psid) l Results At approximately 71.7% power, each Main Steam Isolation valve (MSIV) was l i

stroked. The results at 71.7% power are shown in Tables 25.1 and 25.2.

All acceptance criteria were satisfied. Scram margins were adequate so the test was performed again near the Tech Spec maximum allowed power level (75%) for MSIV closures. All acceptance criteria were satisfied during the MSIV closures at 74% rerate power. The results at 74% power are summarized in Tables 25.3 and 25.4.

I l

l

. . = , . _ . -

Peach Bottom Atomic Power Station 1 i Unit 2 Rerate Startup Test Report Page 44 of 61

STARTUP TEST 25 - MAIN STEAM ISOLATION VALVES (Continued) i TABLE 25.1 i MSIV Closures at 71.7% Rerate Power l l MSIV INDIVIDUAL CLOSURE DATA Close Peak Peak Flux I MSIV Time Pressure (Power) i Closed (Seconds) (psig) (%)

AO-2-02-080A 4.10 1025 79 i

AO-2-02-086A 3.46 1017.5 81 AO-2-02-080B 3.97 1017.5' 79 AO-2-02-086B 3.48 1017.5 82 AO-2-02-080C 4.26 1017.5 80 AO-2-02-086C 3.79 1017.5 80 AO-2-02-080D 4.30 1017.5 79 i

AO-2-02-086D 3.94 1017.5 80 TABLE 25.2 MSIV Closures at 71.7% Rerate Power MSL Peak Flow (paid)

MSIV MSL A MSL B MSL C MSL D CLOSED AO-2-02-080A 0 56 56 52.8 AO-2-02-086A >

0 52.8 52.8 52.8 AO-2-02-080B 52.8 0 54.4 52.8 AO-2-02-086B 51.2 0 54.4 52.8 AO-2-02-080C 54.4 54.4 0 54.4 AO-2-02-086C 52.8 '54.4 0 52.8 AO-2-02-080D 51.2 5'e .8 52.8 0 AO-2-02-086D 51.2 54.4 56 0 l

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Peach Bottom Atomic Power Station  ;

Unit 2 Rerate Startup Test Report Page 45 of 61 STARTUP TEST 25 - MAIN STEAM ISOLATION VALVES (Continued)

TABLE 25.3 MSIV Closures at 74% Rorate Power MSIV INDIVIDUAL CLOSURE DATA Close Peak Peak Flux i MSIV Time Pressure (Power) l Closed (Seconds) (psig) (%)

AO-2-02-080A 4.17 1032.5 83 AO-2-02-086A 3.59 1025 83  ;

I AO-2-02-080B 3.86 1025 83 )

AO-2-02-086B 3.74 1032.5 85 AO-2-02-080C 4.23 1032.5 83 AO-2-02-086C 3.84 1032.5 86 AO-2-02-080D 4.34 1032.5 83 AO-2-02-086D 3.93 1025 83 TABLE 25.4 MSIV Closures at 74% Rerate Power MSL Peak Flow (psid)

MSIV MSL A MSL B MSL C MSL D CLOSED AO-2-02-080A 0 57.6 57.6 57.6 AO-2-02-086A 0 57.6 57.6 57.6 AO-2-02-080B 57.6 0 56.0 57.6 AO-2-02-086B 57.6 0 57.6 57.6 AO-2-02-080C 57.6 60.8 0 57.6 AO-2-02-086C 57.6 57.6 0 57.6 i AO-2-02-080D 57.6 59.2 57.6 0 '

AO-2-02-086D 57.6 57.6 57.6 0 l

1

Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 46 of 61 STARTUP TEST 29 - RECIRCULATION SYSTEM FLOW CONTROL Purcose This test demonstrates the Recirculation system flow control capability of the plant for individual remote manual control operation and determines that all electrical compensators and controllers are set for desired system performance and stability.

Description Prior to rerate implementation, several adjustments to the Recirculation system are required. The cams inside the scoop tube positioners are being modified to ensure adequate incremental regulation of speed demand to generator speed. The scoop tube positioners are calibrated in accordance with Section E81-2-1 of Vendor Manual M-1-JJ-55, and the Voltage Regulator on the MG Sets is calibrated in accordance with IC-11-02033.

The Recirculation system is tested by inserting small positive and

negative speed steps, corresponding to 1% to 5% changes in core flow, in remote manual mode to check speed loop stability. This is done in accordance with MAT 5374B (ARTS /MELLLA Mod Acceptance Test). The electrical and mechanical stops for the extended core flow are adjusted in accordance with RT-I-002-290-2.

];,evel 1 Criteria The transient response of any recirculation system related variable to any test input must not diverge.

Level 2 Criteria

1. A scram shall not occur due to Recirculation flow control maneuvers.

2. The decay ratio of any oscillatory controlled variable must be less than or equal to 0.25.

3. Steady state limit cycles (if any) shall not produce turbine steam flow variations greater than 0.5% of rated steam flow. l

Peach Gottom Atomic Power Station l Unit 2 Rerate Startup Test Report l

Page 47 of 61 i

STARTUP TEST 29 - RECIRCULATION SYSTEM FLOW CONTROL l

Results Several Recirculation system adjustments were requi?.ed prior to operating at rerated conditions. The cams inside che scoop tube positioners were modified during the 2R10 outage to ensure the incremental regulation of speed demand to generator speed is linear within a factor of 2. The scoop tube positioners and the voltage regulator on the MG Sets were calibrated as required for power rerate r conditions.

The high speed stops for the extended core flow were adjusted in accordance with RT-I-002-290-2 at 100% rerate power. During the setting of the high speed stops, Special Procedure SP-2056 was performed to check for containment noise. The test was= completed satisfactorily.

Additional containment noise monitoring will be performed prior to the end of cycle coastdown.

GE recommended that the flow steps for power rerate be performed at 100%

power /100% flow conditions. The ARTS /MELLLA region yields the same power (operating on a higher rod line) with lower recirculation flow; therefore, the same amount of change in recirculation flow will have a more pronounced impact on reactor power in the ARTS /MELLLA region than '

at 100% power /100% flow conditions. For this reason, performing the recirculation stability testing at 97% power /82% flow conditions satisfies the power rerate testing requirements.

Recirculation system stability testing was performed at approximately -

97% power /82% flow conditions. Negative and positive 5% steps in f recirculation flow were input, and system response was recorded. Plant parameter responses to the step changes in recirculation flow were heavily damped with no oscillations and no signs of divergence. All acceptance criteria were satisfied.

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 48 of 61 ETARTUP TEST 33 - TURBINE STOP VALVE SURVEILLANCE TEST Purnose 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-001-400-2 and Special Procedure SP-2028. Based on the initial results from Test Condition 4 (original 100% power) , this test may be performed during Test Conditions 5 and 6.

Level 1 Criteria None.

Level 2 Criteria

1. Peak neutron flux must be at least 7.5% below the scram trip

, setting.

1, j 2. Peak vessel pressure must remain at least 10 psi-below the high j pressure scram setting. (Peak Pressure < 1075 psig)

3. Peak steam flow in the main steam lines must remain 10% below the j high flow isolation trip setting. (Peak steam flow < 110.97 psid)

)

} Results i

j In order to have data from which to extrapolate, Turbine Stop Valve i testing was initially performed at 90% power. All acceptance criteria j were satisfied; therefore, testing could continue at 95% power. The 1

testing at 95% power also satisfied all acceptance criteria. The data I 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.

Prior to increasing reactor power to 97%, EHC Pressure Set was lowered i j

from 950 psig to 940 psig in order to maintain reactor pressure below the rated value of 1035 psig at 100% power. Based on the previous extrapolations and the conservative action of lowering EHC Pressure Set, i testing at 97% power was performed. However, the data obtained during ;

the 97% power test performance could not be extrapolated to 100% power  ;

conditions. The change in EHC Pressure Set invalidated the extrapolation data. {

Test Exception Report (TER) #9 documents this i inability to perform the extrapolation to 100% conditionc.

1 I e

l Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 49 of 61 STARTUP TEST 33 - TURBINE STOP VALVE SURVEILLANCE TEST (Continued) l I

Results (Continued) l Based on the amount of scram margin observed during the 97% power testing, it was determined that testing could be performed at 100% power as long as adequate scram margin was verified prior to stroking the valves. Adequate scram margin was verified, and all Turbine Stop Valves were satisfactorily stroked at 100% power. All acceptance criteria were satisfied; 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.

TABLE 33.1

) Flux Peaks During Turbine Main Stop Valve (MSV) Closures Actual Test Power Levels (%)

91 94.3 97.3 99.85 MSV Test Reactor Peak Power (%)

MSV1 97 99.0 103 105 MSV2 96 97.5 102 105 MSV3 97 100 101 105 MSV4 96 99.5 102 104 ,

TABLE 33.2 Reactor High Pressure Peaks During MSV Closures Actual Test Power Levels (%)

91 94.3 97.3 99.85 MSV Test Reactor Pressure Peak (psig)

MSV1 1033 1041 1035 1042 MSV2 1031 1041 1034 1042 MSV3 1033 1042 1035 1042 MSV4 1031 1041 1034 1042 l

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l Peach Bottom Atomic Power Station

] Unit 2 Rerate Startup Test Report Page 50 of 61 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 57 57 MSV2 57 Downscale 57 59 91 57 MSV3 59 Downscale 59 MSV4 59 57 61 Downscale MSV1 -Downscale 62 63 62 MSV2 63 Downscale 66 64 MSV3 94.3 63 67 Downscale 65 MSV4 66 63 67 Downscale MSV1 Downscale 69 71 70 MSV2 69 Downscale 73 74 MSV3 97*3 69 73 Downscale 74 MSV4 74 73 76 Downscale  ;

MSV1 Downscale 68 71 68 l

MSV2 73 Downscale 77 76 MSV3 99.85 72 77 Downscale 78 MSV4 79 70 76 Downscale i

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Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 51 of 61 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.

Description Individual main turbine valves are tested routinely during plant operation as required for turbine surveillance testing. Turbine Control Valves are individually stroked at various power levels for power rerate in accordance with Special Procedure SP-2029 to determine the highest power at which the normal surveillance testing can be performed. Based on the initial test results from Test condition 4 (original 100% power) ,

this test may be performed during Test Conditions 5 and 6.

Level 1 Criteria None.

Level 2 Criteria

1. Peak neutron flux must be at least 7.5% below the scram trip setting.

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.

Prior to increasing reactor power to 97%, EHC Pressure Set was lowered from 950 psig to 940 psig in order to maintain reactor pressure below the rated value of 1035 psig at 100% power. Based on the previous extrapolations and the conservative action of lowering EHC Pressure Set, testing at 97% power was performed. However, the data obtained during the 97% power test performance could not be extrapolated to 100% power conditions. The change in EHC Pressure Set invalidated the extrapolation data. Test Exception Report (TER) #8 documents this 1 inability to perform the extrapolation to 100% conditions.

Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 52 of 61 STARTUP TEST 34 - TURBINE CONTROL VALVE SURVEILLANCE TEST (Continued)

Results (Continued)

Based on the amount of scram margin observed during the 97% power testing, it was determined that testing could be performed at 100% power as long as adequate scram margin was verified prior to stroking the valves. Adequate scram margin was verified, and all Turbine Control Valves were satisfactorily stroked at 100% power. All acceptance criteria were satisfied; therefore, fature Turbine Control 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 34.1, 34.2, and 34.3.

TABLE 34.1 Flux Peaks During Turbine Control Valve (TCV) Closures Actual Test Power Levels (%)

91 95 97.1 99.94 TCV Test Reactor Peak Power (%)

TCV1 95 98 101 103 TCV2 94 98 101 102 TCV3 96 97 101 102 l TCV4 95 97 100 103 l

TABLE 34.2 Reactor High Pressure Peaks During TCV Closures Actual Test Power Levels (%)

91 95 97.1 99.94 TCV Test Reactor Pressure Peak (psig)

TCV1 1025 1033 1027 1032 TCV2 1025 1033 1026 1032 TCV3 1025 1033 1026 1032 TCV4 1025 1033 1026 1033

.. . . . . = _ _ -. .- - . . _ - - _-___ -__--

I j

. . . I Peach Bottom Atomic Power Station l

l Unit 2 Rerate Startup Test Report I Page 53 of 61 l l

i

! STARTUP TEST 34 - TURBINE CONTROL VALVE SURVEILLANCE TEST (Continued) l

! Results (Continued) 4 i

i TABLE 34.3 MSL Flow Peaks During TCV Closures MSL FLOW Peak (psid) 5 I TCV Test MSL A MSL B MSL C MSL D TEST Power j TCV1 51 51 ~51 51 j l

l TCV2 49 49 51 51  ;

TCV3 81 49 51 51 49 4

TCV4 51 51 51 51 i -

j TCV1 56 57 57 57  ;

i j TCV2 56 57 56 56  !

j TCV3 95 56 58 56 57 j TCV4 56 58 56 57 s

TCV1 56 57 57 57 t

i j TCV2 57 57 57 57 TCV3 97.1 57 57 l 57 57 ,

i j TCV4 57 57 58 56 I

f TCV1 59 59 60 59

] TCV2 60 59 60 59 TCV3 99.94 63 59 60 60 j TCV4 61 60 61 58 J

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i Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 54 of 61 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.

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 flow 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-002-250-2, Core Flow Verification.

Level 1 Criteria None.

l 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%.

l 2. The percent flow signal to APRM and % core flow calculation numbers l must agree within 1%.

Results

( Core Flow Verification was performed at 100% rerate power. Data was l collected, and core flow calculations were performed. The largest deviation between core flow values was -0.84%. All total core flow indications (PMS Point B015, Control Room indicator DPFR-095, and j calculated core flow values) agreed within 2%. APRM % flow numbers  ;

were also calculated and agreed with % core flow calculation numbers within 0.9%. All acceptance criteria were satisfied.

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i l Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 55 of 61 i

STARTUP TEST 72 - DRYWELL ATMOSPHERIC COOLING Puroose 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.

I Descrintion '

Drywell temperature is monitored to ensure design limits are not  ;

exceeded. There are no changes for rerate which will affect the air I 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-530-2, Drywell Temperature Monitoring, at approximately 95% power (original 100% power) and at rerated 100% power.

Level 1 Criteria 1

Drywell temperature shall not exceed 145 F. ,

l Level 2 Criteria Drywell temperature shall not exceed 140 F.

Results At 94.9% 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 128.53 F at 94.9% power and 129.34 F at 100% power. All Level 1 and Level 2 acceptance criteria were satisfied.

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l t Peach Bottom Atomic Power Station

} Unit 2 Rerate Startup Test Report l Page 56 of 61 i

l STARTUP TEST 80 - THERMAL PERFORMANCE DATA COLLECTION Purpose The purpose of this procedure is to collect steady state data at all

test conditions during the plant startup and for an extended period of i seven to nine days at full power following rerate implementation. This j 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.

Description Steady state data on thermal performance parameters is collected and evaluated at steady state conditions at low power (<50%), from 85% to 100%, and for an extended period at 100% rerate power.

Level 1 Criteria None.

Level 2 Criteria None.

Results Data was collected at approximate power levels of 35%, 85% to 95%, and 100%. 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.

' Peach Bottom Atomic Power Station Unit 2 Rerate Startup Test Report Page 57 of 61 STARTUP TEST 81 - SURVEILLANCE TESTING Purpose 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 but two of these surveillance tests were completed prior to startup.

The 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.

Peach Bottom Atomic Power Station

Unit 2 Rerate Startup Test Report i

Page 58 of 61

STARTUP TEST 82 - STEADY STATE DATA COLLECTION Purpose 4

The purpose of this procedure is to collect steady state data during the plant startup following rerate implementation. A portion of this data

! 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.

Description The first two data sets, taken at Test Conditions 2 and 3, include baseline information (for extrapolation) to project operating performance parameters at rerated conditions. Extrapolations of 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 and, when available, either historical or projected performance values. Comparisons to historical data will not j be possible for all parameters based on different plant conditions (i.e.

higher reactor pressure) at the same megawatt thermal power levels.

Data will be collected at approximately the following rerated power levels:

TEST CONDITION ORIGINAL POWER RERATE POWER LEVEL RERATE MWT LEVEL (%)

2 89.3% - 90.3% 85%-86% 2939 - 2974 3 94.5% - 95.6% 90%-91% 3112 - 3147 4 99.8% - 100.8% 95%-96% 3285 - 3320 5 N/A 97%-98% 3354 - 3389 6 N/A 99%-100% 3423 - 3458 Level 1 Criteria None.

Level 2 Criteria None.

s*. o Peach Bottom Atomic Power Station i Unit 2 Rerate Startup Test Report Page 59 of 61 I

STARTUP TEST 82 - STEADY STATE DATA COLLECTION (Continued)

Results Data was recorded for over 160 p10nt parameters at Test Conditions 2 through 6. For the most part, the data recorded tracked very well with the predicted and/or historical values. Where data did not track with either the predicted or historical values, discrepancy forms were filled out. Several Action Requests were initiated to investigate instruments that were reading incorrectly. Observations were made during Test conditions 3 and.4 that reactor pressure was indicating higher than predicted by about 15 psig. Concerns were raised about exceeding rated reactor pressure of 1035 psig when the reactor achieved 100% power.

Discussions were held and evaluations performed concerning reactor pressure being close to the expected rerated value when the plant was operating at 95% (original 100%) power. Chesterbrook Engineering headed up the discussion and proposed resolutions. EHC pressure set was set at 950 psig for power rerate conditions based on the final design rerated reactor pressure increase of 30 psi. Previously, EHC pressure set was set at 920 psig.

l The resolution to this issue was to decrease EHC pressure set to 940 psig and take data in accordance with rerate Special Procedure SP-2034, Steady State Data Collection. If the data collected is acceptable, revisions will be made to General Plant procedures to set EHC pressure set such that reactor pressure at 100% power does not exceed 1035 psig and Turbine Control Valve positions remain less than 65% open.

Temporary changes were made to the applicable plant procedures, and EHC Pressure Set was lowered to approximately 940 psig with reactor power remaining at 95%. SP-2034 was performed to collect data for comparison to the previous data collected at 95% power with EHC Pressure Set at 950 psig. The data was acceptable. Reactor pressure dropped 8 psig. Total l Control Valve position increased by 3%. Power ascension continued with r reactor pressure and turbine control valve positions monitored closely.

t EHC Pressure Set remained at 940 psig.

The data collected at Test Conditions 5 and 6 tracked well with predicted values. Reactor pressure at 100% was 1031 psig (using the control Room indication) . Individual control valve positions ranged from 59.7% to 63.9%. The total control valve position was 62%. This exceeded the prediction by only 3% which can be accounted by the l decrease in EHC Pressure Set.

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