ML20210A404

Ei Hatch Nuclear Plant Unit 1,Extended Power Uprate Startup Test Rept for Cycle 19

ML20210A404
Person / Time
Site:	Hatch
Issue date:	07/15/1999
From:	Long T, Mcelroy G SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20210A388	List: HL-5808, Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage ML20210A404
References
NUDOCS 9907220095
Download: ML20210A404 (30)

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EDWIN 1. IIATCII NUCLEAR PLANT UNIT 1 EXTENDED POWER UPRATE STARTUP TEST REPORT for CYCLE 19 Prepared by:

W Date: 07//f/94 U . Wy. ng f /

Extended Power Uprate Project Manager j 1

Approved by: A V Date:'7bfb9 G. K. McE)(oy Engineering Mansger 9907220095 990715 PDR ADOCK 05000321 P PDR l

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a 4 Edwin I. Ilatch Nuclear Plant - Unit 1 l Extended Power Uprate Startup Test Report I for Cycle 19 Table of Contents l

Section Pagg 1.0 Executive Summary. . . . . . . . . . E-1 2.0 Purpose .. . .. ... .. . . . .E-2 3.0 Program Description . . ..E-2 4.0 Acceptance Criteria.. .. . . . . .E-3 5.0 Extended Power Uprate Startup Test Program Summary . .E-3 l

6.0 Testing Requirements. . . . . E-4 6.1 FSAR Section 13.6 Tests Not Required for. . .E-4 Extended Power Uprate 6.2 FSAR Section 13.6 Tests Required for., .. . .E-12 Extended Power Uprate 6.3 Additional Tests . .. .. . . . E-20 Tables 1 Unit 1 FSAR Section 13.6 Tests.. . . . . . . . . . . . . .. .E-22 2 Test Conditions. . . . . . . .. . ... .E-24 3 Tests Performed for Extended Power Uprate.. . . .. ..E-25 4 Pressure Regulator "A" Step Change Results. , . .. .. . E-26 5' Pressure Regulator "B" Step Change Results . . . ..E-27 E!strgs 1 Power / Flow Map . . . . . .E-28 HL-5808 i

ENCLOSURE EDWIN 1. HATCil NUCLEAR PLANT - UNIT 1 l EXTENDED POWER UPRATE STARTUP TEST REPORT FOR CYCLE 19 l

1.0 EXECUTIVE

SUMMARY

The Plant Hatch Unit i Extended Power Uprate Startup Test Report is submitted to the Nuclear Regulatory Commission (NRC) in accordance with regulatory commitments contained in Unit 2 Final Safety Analysis Report (FSAR) Section 13.6.4. The report summarizes the startup testing performed on Unit I following implementation of extended power uprate during the eighteenth refueling outage. Extended power uprate was implemented in accordance with Amendment No. 214 of Facility Operating License No. DPR-57.

Unit I was previously licensed to operate at a maximum reactor power level of 2558 MWt. The result of the extended power uprate program is a licensed power increase of 8% The extended power uprate program followed an initial uprate program of 5% from the original licensed power level of 2436 MWt. The total increase in licensed reactor power from the original 2436 MWt to the extended power uprate level of 2763 MWt is 13.42% All testing specified in Unit 1 FSAR Section 13.6 was addressed and evaluated for applicability to the new licensed power level.

The extended power uprate licensed thennal power represents the level at which all safety analyses and engineering evaluations were performed. cycles. The power ascension testing program I

included seven Test Conditions starting with the original licensed power level up to the new 100%

licensed power level of 2763 MWt. All tests were complete up to Test Condition 7, which represents 100% of the new licensed power level. Results of the testing and data gathering demonstrated successful operation at the full licensed power level.

The Reactor Mode Switch was placed in STARTUP on April 24,1999. The final synchronization to the grid was performed on May 1,1999, marking the official end of the Unit i eighteenth refueling outage. All required extended power uprate startup tests were completed by May 20,1999. Special purpose procedures were written and implemented in combination with various surveillance test procedures described in this report. No unusual online adjustments were required for the following plant systems:

. Electrohydraulic Control (EHC) - Pressure Regulation.

. Feedwater.

. Reactor Recirculation.

. Reactor Core Isolation Cooling (RCIC).

. High Pressure Coolant Injection (HPCI).

All systems performed in a stable manner during both plant startup and transient testing. The unit is operating satisfactorily at the new licensed power level. '

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Enclosure Edwin 1. IIatch Nuclear Plant - Unit 1 Extended Power Uprate Startup Test Report for Cycle 19 2.0 PURPOSE This report, which is submitted in accordance with regulatory requirements, summarizes the testing performed on Unit I following the implementation of extended power uprate, which resulted in an increase in licensed reactor power equal to 13.42% of the original rated thermal power (RTP). The purpose of the Plant Hatch Unit I extended power uprate startup tests was to perform the applicable testing specified in Unit 1 FSAR Section 13.6. All testing specified in the FSAR was evaluated for applicability to the new increased licensed power rating. Each test performed for extended power uprate is described in Section 6.0. Satisfactory completion of the startup tests demonstrated the acceptable performance of Unit I following the implementation of extended power uprate.

3.0 PROGRAM DESCRIPTION  !

The extended power uprate startup testing requirements were developed primarily from:

. Review of Unit 1 FSAR Section 13.6.

. Section 10.4 of the General Electric (GE) Extended Power Uprate Safety Analysis Report for Edwin I. Hatch Nuclear Plant Units I and 2.

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. GE Uprate Test Program recommendations.

The testing was conducted following the Unit i eighteenth refueling outage. The results of this testing verified the unit's ability to operate at 100% licensed thermal power. Where possible, testing took credit for existing surveillance procedures. Table I lists the FSAR Section 13.6 stanup tests and delineates the testing performed for extended power uprate.

The majority of testing falls within the following categories:

. Verification the control systems (i.e., Condensate and Feedwater, EHC - Pressure Regulation, and Reactor Recirculation) are stable at extended power uprate conditions.

. Collection of data (i.e., radiation surveys, thermal performance, and plant steady-state) for comparison to previous plant rated conditions.

Table 2 presents the seven Test Conditions at which stanup testing was performed. 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. Testing at a given Test Condition was completed prior to proceeding to the subsequent Test Condition. Prior to increasing power, the Test Lead's approval was required, and prior to exceding the old rated power level of 2558 MWt, the General Manager's approval was required.

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Enclosure Edwin I. Hatch Nuclear Plant - Unit 1 i Extended Power Uprate Startup Test Report for Cycle 19 4.0 ACCEPTANCE CRITERIA

1. Level 1 Variable or Criteria Data trend, singular value, or information relative to a Technical Specifications margin and/or plant design in a manner that requires strict observance to ensure the safety of the public, safe operation of the plant, continued operation at power, worker safety, and/or equipment protection.

Failure to meet Level I criteria constitutes failure of the specific test. The Test Lead is required to resolve the problem, and if necessary, the test is repeated.

2. Level 2 Variable or Criteria Data trend, singular value, or information relative to system or equipment performance that does not fall under the definition of Level I criteria.

Level 2 criteria do not constitute a test failure or acceptance; they serve as infonnation only.

5.0 EXTENDED POWER UPRATE STARTUP TEST PROGRAM

SUMMARY

The test program began when the Mode Switch ivas placed in STARTUP on April 24,1999, and I ended with all required extended power uprate startup tests complete on May 20,1999. The unit was synchronized to the grid on May 1,1999, marking the ofTicial end of the Unit i eighteenth refueling outage. On May 19,1999, the new oprated power level of 2763 MWt was first achieved.

The unit operates satisfactorily at 100% of the new licensed power level. No unanticipated online adjustments were required to control the following systems:

. EHC - Pressure Regulation.

. Reactor Recirculation.

. RCIC.

. HPCI.

All systems performed in a stable manner. Data collected at uprated conditions showed the increase in reactor power has little efTect on reactor water chemistry and radiological conditions throughout the plant.

Table 3 identifie3 all the required extended power uprate startup tests and the Test Conditions in which each test was performed. No Level I test failures occurred.

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Enclosure -

Edwin 1. Ilatch Nuclear Plant - Unit 1 Extended Power Uprate Startup Test Report for Cycle 19 6.0 TESTING REQUIREMENTS Each of the tests discussed in Unit i FSAR Section 13.6 was evaluated for applicability to extended power uprate. Throughout the following discussion, the test numbers and titles, and format are consistent with the FSAR.

1. Section 6.1 - This section identifies each Section 13.6 test not required to be performed for extended power uprate. The purpose of the test and the rationale for exempting the test from the power uprate program are discussed.

2. Section 6.2 - This section identifies each Section 13.6 test required to be performed for extended power uprate. The purpose of the test, a description of the test, Acceptance Criteria, and the test results are included.

3. Section 6.3 - This section identifies additional test / data collection that was performed to assess the performance of the unit at extended power uprate conditions. The purpose of the test, a description of the test, and the test results are included.

Table 1 identifies all the Section 13.6 tests and their applicability to extended power uprate.

Table 2 lists the seven Test Conditions and the associated percent oflicensed power level. Table 3 lists the Section 13.6 tests performed for extended power uprate and the Test Condition (s) for each test. Note that many surveillance tests similar to the original FSAR Chapter 13 tests are performed periodically, often during each startup. Therefore, the extended power uprate test program takes credit for many existing plant procedures.

6.1 FSAR Section 13.6 Tests Not Reauired for Extended Power Unrate 6.1.1 Test (3)- Fuel Loading This test demonstrates the ability to safely and efliciently load fuel to the full core size. Fuel loading is performed during every refueling outage in accordance with site procedures.

Extended power uprate has no impact on this evolution; therefore, no additional testing was required for extended power uprate.

6.1.2 Test (6)- Source Range Monitor Response and Control Rod Sequence j The source range monitor (SRM) portion of this test demonstrates that the operational sources, i SRM instrumentation, and rod withdrawal sequences provide adequate information to the operator l during startup. The Technical Specifications and plant procedures ensure proper SRM response i during startup, This portion of Test (6) was not performed for extended power uprate.

The control rod sequence portion of Test (6) demonstrates the ability to achieve, in a safe and eflicient manner, criticality for each of the specified withdrawal sequences. The effect of rod liL-5808 E-4 i

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Enclosure Edwin I. IIatch Nuc! car Plant - Unit i Extended Power Uprate Startup Test Report for Cycle 19 I

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motion on reactor power at various operating conditions is also determined. Extended power uprate does not change the manner in which criticality is achieved. The rod patterns for intermediate power levels up to the applicable power level are evaluated using a three-dimensional simulator code. This portion of Test (6) was not specifically required for extended power uprate.

l l i l 6.1.3 Test (7)-Intermediate Range Monitor Performance i This test ensures the ability to adjust the intermediate range monitors (IRMs) to obtain optimum overlap with the SRMs and the average power range monitors (APRMs). The Technical l Specifications and plant procedures ensure proper IRM response during startup. This test was not specifically repeated for extended power uprate.

I 6.1.4 Test (10)- Process Computer This test verifies the performance of the process computer under plant operating conditions.

, Extended power uprate does not affect the ftmetions of the process computer; however, some input variables required modification. This test was not specifically required for extended power uprate.

6.1.5 Test (11)- Reactor Core Isolation Cooling System I This test verifies the proper operation of the RCIC System and provides baseline data for future surveillance testing. Acceptable RCIC System operation is periodically demonstrated during normal surveillance testing that includes adjustments for reactor dome pressure and the lowest safety relief valve (SRV) setpoint. Since extended power uprate is accomplished without changing reactor pressure, special testing was not required for extended power uprate.

6.1.6 Test (12)-liigh Pressure Coolant Injection System This test verifies the proper operation of the HPCI System at the operating pressure ane : 9vides baseline data for future surveillance testing. Acceptable HPCI System operation is periodically demonstrated during normal surveillance testing that includes adjustments for reactor dome pressure and the lowest SRV setpoint. Since extended power uprate is accomplished without changing reactor pressure, special testing was not required for extended power uprate.

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F l Enclosure Edwin I. Hatch Nuclear Plant - Unit 1 l Extended Power Uprate Startup Test Report for Cycle 19 j i

6.1,7 . Test (13)- Selected Process Temperatures i

i j This test establishes the minimum recirculation pump speed needed to maintain water temperature in the bottom head of the reactor pressure vessel (RPV) within 145 F of the reactor coolant saturation temperature determined by reactor pressure. This test ensures the measured bottom head drain line thermocouple is adequate to measure the bottom head coolant temperature during l normal operations. Temperature stratification limits are defined in the Technical Specifications.

l This test was not required for extended power uprate.

6.1.8 Test (14)- System Expansion This test verifies reactor drywell piping and major equipment are unrestrained with regard to thennal expansion. An analysis for extended power uprated conditions indicated the piping systems were acceptable for extended power uprate; therefore, further testing was not required.

6.1.9 Test (15)- Core Power Distribution ,

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This test determines core power distribution in three dimensions, confirms reproducibility of Traversing Incore Probe (TIP) System readings, and determines core power symmetry. Existing site procedures verify proper TIP operation and core power synunctry. Extended power uprate l l does not significantly impact these parameters. TIP operation is not affected by extended power uprate.

6.1.10 Test (17)- Steam Production This test demonstrates the ability to operate continuously at rated reactor power, demonstrating l that the Nuclear Steam Supply System (NSSS) provides steam at a sufficient rate and quality.

This test is the initial warranty run, which is not applicable to extended power uprate.

6.1.11 - Test (18)- Flux Response to Rods This startup test demonstrates stability in the power reactivity loop with increasing reactor power and determines the effect of control rod movement on reactor stability. Extended power uprate had only a minor impact on stability margin; operation on a slightly higher flow control (rod) line is allowed. However, no testing related to thermal-hydraulic stability was performed for extended power uprate. Routine operation in the high power / low flow corner of the power-to-flow map is no longer permitted due to concerns over thermal hydraulic stability.

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Enclosure l Edwin 1. Hatch Nuclear Plant - Unit 1 l Extended Power Uprate Startup Test Report for Cycle 19 6.1.12 Test (20)- Feedwater System l The five objectives of this staitup test are to:

. Demonstrate RPV water level control. I

. Evaluate and adjust feedwater controls. l

. Demonstrate the capability of the automatic flow runback feature to prevent a low water level scram following a single RFP trip.

. Demonstrate adequate response to feedwater heater loss.

. Demonstrate general reactor response to inlet subcooling changes.

During initial startup, these objectives were demonstrated through the performance of different tests. The tests performed specifically for extended power uprate are included in Section 6.2.9.

The tests that were not performed for extended power uprate are as follows:

1. Loss of Feedwater Heatine (LOFH)

The LOFH test performed during initial startup testing demonstrates adequate response to LOFH. The transient event is caused by an equipment failure or operator error that causes isolation of one or more feedwater heaters. Plant-specific transient analyses from previous cycles show acceptable response relative to fuel thermal limits; i.e., minimum critical power ratio (MCPR) and fuel cverpower.

The LOFH transient was reanalyzed for extended power uprate, and fuel thermal limits were acceptable. Therefore, the LOFH test was not required for extended power uprate.

2. Sinele Reactor RFP Trin This test verifies the capability of the automatic recirculation pump nmback to prevent a low water level scram following a single RFP trip. The only impact of extended power uprate on this design feature is that extended power uprate allows operation on a slightly higher flow control (rod) line. Therefore, the core power level will be slightly higher following the recalculation runback. This increase in power requires slightly higher flow from the remaining RFP to maintain level.

Prior to startup, transient analyses were performed to determine the required capacity of the remaining RFP. During startup, the actual pump capacity was verified to be larger than

, required for extended power uprate conditions. Therefore, tripping an RFP at high power l

was not necessary for extended power uprate.

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1 Enclosure Edwin 1. Hatch Nuclear Plant - Unit 1 l Extended Power Uprate Startup Test Report for Cycle 19 6.1.13 Test (21)- Bypass Valves l

This test demonstrates the ability of the pressure regulator to minimize disturbances to the reactor during an abrupt change in reactor steam flow. This test also demonstrates that I

the turbine bypass. valves can be functionally tested at or near rated power without causing a scram.

Bypass valves are routinely tested at high power, and response time tested prior to startup.

Extended power uprate operation will not change bypass valve operation. Therefore, this startup test was not performed specifically for extended power uprate.

6.1.14 Test (22)- Main Steam Isolation Valves The three objectives of this test are to:

. Functionally check the main steam isolation valves (MSIVs) for proper operation at selected power levels.

. Determine reactor transient behavior during and following simultaneous full closure of all MSIVs and following closure of one MSIV.

. Determine MSIV closure times.

Severe transient testing performed at high power during the initial startup demonstrates the adequacy of protection for these severe transients. Analysis shows that should these transients occur at extended power uprate conditions, the change in unit performance will be small; therefore, testing the unit's response to full closure of the MSIVs at the uprated power level was not required.

MSIVs will continue to be surveillance tested per existing site procedures.

6.1.15 Test (23)- Safety Relief Valves This test verifies proper operation of the dual-purpose SRVs, including determination of capacity and verification ofleaktightness following operation. SRV capacity was not affected by extended power uprate. This startup test, as described in the FSAR, was not specifically performed for extended power uprate.

6.1.16 Test (24)- Turbine Trip and Generator Load Rejection Demonstration This test demonstrates the response of the reactor and its control systems to protective trips initiated by the turbine and generator. Severe transient testing performed at high power levels during the initial startup demonstrated the adequacy of protection for these severe transients.

Analysis shows that should these transients occur at uprated conditions, the change in unit l

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Enclosure Edwin I. Hatch Nuclear Plant - Unit i Extended Power Uprate Startup Test Report for Cycle 19 performance will be small; therefore, testing the unit's response to turbine and generator trips at extended power uprate conditions was not required.

6,1,17 Test (25)- Shutdown from Outside the MCR This test demonstrates the ability to shut down the reactor from nonnat steady-state operating conditions to the point where cooldown is initiated and under control with reactor pressure and water level controlled from outside the main control room (MCR). Extended power uprate does

,not alter the capability of the reactor to be shut down from outside the MCR; therefore, this test was not repeated for extended power uprate.

6.1.18 Test (26)- Flow Control This test determines the plant's response to changes in recirculation flow and thereby, adjusts the local control loops. .Also, the load following capability of the plant is established. Extended power uprate does not significantly affect either the recirculation flow control system or the licensed maximum core flow limits. Therefore, the recirculation flow control startup test was not required for extended power uprate.

6.1.19 Test (27)- Recirculation System The two objectives of this test are to:

. Determine the transient responses and steady-state conditions following recirculation pump trips (RPTs) and obtain jet pump performance data.

. Verify no recirculation system cavitation occurred.

This test determines the transient response during RPTs, flow coastdown, and pump restarts.

Extended power uprate does not affect the ability of the Recirculation System to respond acceptably to these transients, as demonstrated during the initial startup test program. Therefore, further testing for extended power uprate was not required.

Extended power uprate modified the logic to speed limiter no. 2 to improve the plant's response to a single RFP event. A third runback feature was also implemented during the Unit I outage as a plant reliability feature. The third runback occurs on sensing low condensate booster or RFP suction pressure prior to the existing resocctive pumps' low suction trips. These features were functionally tested during startup testing as part of the design modification implementation procedures. Acceptable performance was demonstrated via the functional tests.

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Enclosure Edwin I. Hatch Nuclear Plant - Unit 1 Extended Power Uprate Startup Test Report for Cycle 19

. 6.1.20 Test (28)- Loss of Turbine Generator and Offsite Power This test demonstrates proper performance of the reactor, and plant electrical equipment and systems during the loss of auxiliary power transient. Extended power uprate does not change the

' ability of the electrical systems to function properly during a loss of the main turbine-generator and a loss of offsite power (LOSP). The ability of the reactor systems (e.g., HPCI and RCIC) to function properly afi. prated conditions was demonstrated during normal system surveillance procedures. This test was not specifically required for extended power uprate.

6.1.21 Test (30)- Vibration Measurements This initial startup test demonstrates the mechanical integrity of the reactor system under conditions of flow-induced vibration by taking vibration measurements correlating it to analytical models. The impact of extended power uprate on reactor intemals vibration was evaluated at extended uprated power and maximum core flow. The maximum licensed core flow was not increased for extended power uprate, and it was determined the reactor vessel internals design continued to comply with existing structural requirements. The 8% change in power was not expected to affect the internals vibration levels enough to warrant extensive testing.

6.1.22 Test (31)- Main Turbine Stop Valve Surveillance Test The purpose of this original startup test is to demonstrate acceptable procedures for turbine stop valve surveillance tests at a power level as high as possible without producing a reactor scram.

Plant Hatch has years of experience testing turbine stop and control valves. During the extended power uprate startup, the valves were tested using existing site procedures at power levels and pressures where experience shows no problems occur. Therefore, this startup test was not

performed for extended power uprate.

M.23 Test (32)- Recirculation and Jet Pump Instrument Calibration

. The purpose of this initial startup test is to obtain an integrated calibration of the installed jet pump and recirculation pump flow instrumentation with the reactor shutdown prior to jet pump flow calibration. Extended power uprate does not significantly affect the ability to calibrate this i instrumentation; therefore, this test was not repeated for extended power uprate. )

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6.1.24 .. Test (33)- RWC System i This test demonstrates the specific aspects of the mechanical operability of the Reactor Water l Cleanup (RWC) System. Detailed evaluations show the impact of the new licensed power causes i minor changes in RWC System operating requirements. These changes are well within the j system's design parameters. No specific RWC testing was performed for extended power uprate. 1 HL-5808 E-10

, , i t Enclosure i Edwin 1. Hatch Nuclear Plant - Unit 1 I ' Extended Power Uprate Startup Test Report for Cycle 19 6.1.25 ' Test (34) - RHR System Thir test demonstrates the ability of the Residual Heat Removal (RHR) System to:

. Remove decay heat from the NSSS so refueling and servicing can be performed.

. Condense steam while the reactor is isolated from the main condenser.

The capability of the RHR System to remove residual and decay heat has been demonstrated many times over the years. Extended power uprate's effect on system performance is a small increase in reactor cooldon time. The RHR System will continue to perform acceptably. The steam condensing mode of RHR has been removed and thus, is not a factor. Therefore, the RHR System startup test was not performed for extended power uprate.

6.1.26 Test (35)- Drywell Atmosphere Cooling l

This startup test demonstrates the ability of the primary containment cooling system to maintain drywell temperatures within the temperatures assumed in the safety analysis.

Extended power uprate was expected to have a minimal impact (1 to 2 F) on drywell temperature.

Extended power uprate itself does not afTect the cooling system significantly and will not require the cooling system to be operated differently. Therefore, no additional testing for uprate was performed.

6.1.27 Test (36)- Cooling Water Systems The purpose of this test was to verify the performance of the reactor and turbine building closed cooling water, and service water systems was adequate with the reacter at rated temperature. The impact of extended power uprate operation on these systems was evaluated and found to be small.

Modifications were made to the main generator stator cooling system to maintain adequate design margins. Selected steady-state temperature data for specific loads (e.g., main generator stator and isophase bus cooling) were obtained during startup; however, no specific uprate tests were performed.

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1 Enclosure Edwin I. Hatch Nuclear Plant - Unit !

Extended Power Uprate Startup Test Report for Cycle 19 6.2 FSAR Section 13.6 Tests Reauired for Extended Power Unrate 6.2.1' Test (1) - Chemical and Radiochemical Tests

Purpose:

To determine the effects of extended power uprate on reactor coolant chemistry.

Descrintion: Chemical and radiochemical samples were taken in accordance with plant procedures at 92.5%,95%,97.2%,98%,99%, and 100% of the new licensed power level.

Acceptance Criteria: Level /: Per Procedure 60AC-HPX-010-0S, Plant Sampling and Monitoring Program, and the Unit 1 Technical Requirements Manual (TRM).

Level 2: None. l Results: Procedure 60AC-HPX-010-OS was performed satisfactorily at 92.5%,95%,

97.2%,98%,99%, and 100% of the new licensed power level. All Acceptance i Criteria were satisfied, and results indicate an expected acceptable performance at 100% of the new licensed power level, Chemistry data, as shown below, for extended power uprate were taken at normal i water chemistry conditions.

Chemistry Results Primary Reactor Acceptance Coolant Actual Data Criteria  !

92.5 % 95 % 97.2 % 98 % 99 % 100 %

Conductivity 2

0.197 0.200 0.200 0.182 0.162 0.158 s 2.0

( mhos/cm )

Chlorides

• 2.1 1.7 1.5 0.9 1.0 0.9 s200 (ppb)

' Grab sample.

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Enclosure Edwin I. Ilatch Nuclear Plant - Unit 1 Extended Power Uprate Startup Test Report for Cycle 19 6.2.2 Test (2)- Radiation Measurements Purpose. To measure radiation levels at selected locations and power conditions during plant operation to ensure the protection of plant personnel and continual compliance with 10 CFR Part 20.

Msgription: Radiation levels were measured in accordance with plant procedures at various locations within the plant at 92.5%,95%,97.2%,98%,99%, and 100% of the new licensed power level.

Acceptance Criteria: /sevel1: Radiation doses of plant origin and occupancy times of personnel in radiation zones are controlled consistent with the guidance of 10 CFR 20, Standards for Protection Against Radiation.

Level 2: None.

Results: Radiation surveys were conducted at normal water chemistry conditions. The dose rates were comparable to those experienced at the previous licensed power level. No postings were changed as a result increasing power. Radiation dose rates remain complaint with the10 CFR Part 20 limit.

6.2.3 Test (4)- Shutdown Margin Purpose To demonstrate that throughout the fuel cycle, the reactor will be suberitical with the analytically detennined highest-wonh control rod capable of being fully withdrawn and all other rods fully insened.

D scrintion: Shutdown margin (SDM) demonstrations were perfonned in accordance with Procedure 42CC-ERP-010-0S, Shutdown Margin Demonstration. The demonstration was performed analytically during the Cycle 19 beginning of cycle (BOC), and using an insequence critical control rod with the reactor core in a Xenon-free state. Correction factors were used to adjust to startup conditions.

Acceptance Critena bevel 1: SDM is 2 0.38% A k/k + R, as specified in the Technical Specifications and Procedure 42CC-ERP-010-OS.

Level 2: None.

Results: For Unit 1 Cycle 19, the required SDM was 2 0.38% Ak/k + R. (SDM is lowest at BOC conditions; therefore, R = 0%.) Demonstration of SDM was performed during withdrawal of an insequence control rod rather than solely by calculation.

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Enclosure Edwin 1. Hatch Nuclear Flant - Unit 1 Extended Power Uprate Startup Test Report for Cycle 19 As Unit I reached criticality, SDM was calculated in accordance with Procedure 42CC-ERP-010-0S. Cycle 19 SDM was determined to be 1.552% Ak/k, thus satisfying the Level 1 Acceptance Criteria.

6.2.4 Test (5)- Control Rod Drive Purposs: To demonstrate the control rods meet Technical Specifications requirements for scram times.

Description:

Scram timing of control rods was performed in accordance with Procedure 42SV-Cl 1-003-0S, Control Rod Scram Testing. Control rod drive (CRD) timing was perfonned in accordance with Procedure 34SV-Cl 1-004-IS, CRD Timing.

Acceptance Criteria: Level 1: Per Procedure 42SV-Cl1-003-0S and applicable Technical Specifications.

Level 2: Per Procedure 34SV-C11-004-1S.

Results: Scram time testing was performed for selected control rods during either the RPV leakage test or < 40% oflicensed thermal power. Per Procedure 42SV-Cl1-003-0S, all Level 1 Acceptance Criteria were satisfied. The Scram Time Acceptance Criterion is the required scram insertion time from the fully withdrawn position to the specified notch position. The results of the average notch insertion times for all rods are shown below. An individual control rod that fails to meet criteria is declared a SLOW rod. Ilowever, all 137 control rods met  ;

the Acceptance Criteria.

Scram Time Testing Results f

l Position Inserted Average Notch from insertion Time Acceptance Criteria Fully Withdrawn (sec) (sec) 46 0.283 0.440 36 0.830 1.080 26 1.391 1.830 06 2.550 3.350

, CRD timing data for insertion and withdrawal speeds met the Level 2 Acceptance Criteria of 38.4 see to 57.6 see specified in Procedure 34SV-Cl1-004-IS. For CRDs with an adjusted drive speed, the criteria ranged from 43.2 see to 52.8 sec.

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Enclosure Edwin 1. Ilatch Nuclear Plant - Unit i Extended Power Uprate Startup Test Report for Cycle 19 The withdrawal speed of control rod 18-31 could not be adjusted within the timing criteria. An engineering evaluation was perfonned and the results indicated the condition will nat impact the rod withdrawal error analysis.

6.2.5 Test (8)- Local Power Range Monitor Calibration Purpose To calibrate the local power range monitors (LPRMs).

Description:

The LPRM channels were calibrated to make the LPRM readings proportional to the neutron flux in the narrow-narrow water gap at the chamber elevation. This calibration was performed in accordance with Procedures 34SO-C51-001-0S, TIP System Operation; 42CC-ERP-003-0S, LPRM Calibration Current Calculation; and 42CC ERP-014-OS, Reactor Engineering Cycle Startup Tasks.

Acceptance Criteria: /,cvel /: Per Procedure 42CC-ERP-003-0S.

Level 2: None.

Results: Using site procedures, LPRMs were successfully calibrated at 100% of the new licensed power level. Average LPRM gain adjustment factor values for all operable LPRM channels were within specified limits.

6.2.6 Test (9)- Average Power Range Monitor Calibration Pprnose: To calibrate the APRMs to actual core thermal power, as determined by a heat balance.

Description:

Each APRM channel reading was adjusted to be consistent with core thermal power, as determined by the heat balance. This calibration was performed in accordance with Procedure 34SV-SUV-021-0S, APRM Adjustment to Core Thennal Power.

Acceptance Criteria: Level 1: At least two or more APRMs per RPS trip system are calibrated to RTP. These readings agree with heat balance values within 2%.

Level 2: None.

Besults: APRM gain adjustments were performed at different power levels during the Extended Power Uprate Startup Test Program. Each adjustment was completed satisfactorily, and no problems occurred during the tests.

1-IL-5808 E-15

Enclosure Edwin I. Hatch Nuclear Plant - Unit 1 Extended Power Uprate Startup Test Report for Cycle 19 6.2.7 . Test (16)- Core Performance Purpmg: To evaluate core perfonnance parameters to ensure plant thermal limits are maintained during the ascension to isted conditions.

Descriotion: Core thermal power was measured at all Test Conditions up to 99.3% cf the new rated power, using the current plant methods of monitoring reactor power.

In accordance with Procedure 34SV-SUV-020-0S, Core Parameter Surveillance, demonstration of the fuel thermal margin was performed at each Test Condition.

Fuel thermal margin was projected to the next test point to show expected acceptance margin and was satisfactorily confirmed by the measurements taken at each test point before advancing further, Acceptance Criteria: Level 1: The following thermal limits are < l.000:

. MFLPD (Maximum Fraction of Limiting Power Density).

. MFLCPR (Maximum Fraction of Limiting Critical Power Ratio).

. MAPRAT (Maximum Average Planar Linear Heat Generation Rate Fraction).

Izvel 2: None.

Results: Thennal limits were continuously monitored during power ascension. The surveillance procedure was performed satisfactorily at each Test Condition, thus meeting all Acceptance Criteria. Results of various power levels are as follows:

Thermal Limit Power Levels Power Level Thermal Limit 84 % 92.7 % 94.8 % 97 % 98 % 99 % 99.3 %

MFLCPR 0.864 0.944 0.944 0.912 0.913 0.915 0.964 MFLPD 0.774 0.844 0.843 0.846 0.853 0.861 0.886 MAPRAT 0.843 0.881 0.878 0.895 0.878 0.895 0.938 6.2.8 Test (19)- Pressure Regulator Purpose 1. To confirm recommended pressure control system tuning parameters provide acceptable performance by analysis of the transients induced in the reactor pressure control system by means of pressure step input to the pressure regulators.

IIL-5808 E-16

Enclosure Edwin 1. Ilatch Nuclear Plant - Unit i Extended Power Uprate Startup Test Report for Cycle 19

2. To demonstrate affected plant parameters are within acceptable limits during pressure regulator-induced transients.

3. To verify variation in incremental regulation is within acceptable limits (linear).

Description:

The pressure regulator testing was performed in accordance with Special Purpose Procedure 03SP-041999-SA-1-IS, EHC Pressure Regulator Test for Extended Power Uprate. The pressure control system settings were verified to be within the acceptable limits per the guidance of Service Information Letter (SIL) 589,

" Pressure Regulator Tuning."

During startup, 3- and 6-psi step changes in reactor pressure were simulated, and the resulting transients were recorded. The data for each step change were analyzed for acceptable perfonnance and scram margins prior to performing the next increased pressure step change. Step changes were first perfonned with pressurc regulator "A"in control and second with pressure regulator "B" in control. This test was performed at power levels of 74.5%. 84.8%, and 95%.

Starting r.t ~ 150 MWe, steam flow, MWe, first-stage pressure, and pressure regulator output (E t) were recorded at every 2% power increase up to 100% of the new licensed power level. The data were plotted to confinn pressure regulation linearity.

Acceptance Criteria: Level /: The transient response of the turbine inlet (throttle) pressure to any i test input cannot diverge (decay ratio 5 l). This can be visually verified by observing that the successive peaks of the same polarity are of equal or decreasing amplitude.

Level 2: 1. The decay ratio of the turbine inlet (throttle) pressure is 5 0.25 when operating above the minimum core flow of the master flow control range. Below the minimum core flow, the decay ,

ratio must be 5 0.50. The decay ratio of each control system l should be adjusted to 5 0.25, unless a performance loss at higher power levels is identified.

2. The response time from pressure setpoint input until the pressure peak of the turbine inlet pressure is 510 sec.

3. Pressure control system deadband and delay are small enough that steady-state limit cycles (if any) produce steam flow variations no larger than 10.5% of rated steam flow.

4. Peak vessel neutron flux and pressure remain below scram settings by 7.5% and 10 psig, respectively.

11L-5808 E-17

Enclosure Edwin I. Hatch Nuclear Plant - Unit 1 Extended Power Uprate Startup Test Report for Cyc!c 19 Resulty Selected data obtained during each Test Condition are summarized in the Tables 4 and5.

The system response to step changes at each power level was satisfactory. No signs of divergence or oscillations occurred. Pressure response time and margins to scram setpoints were adequate in all cases. No limit cycles were observed. All Level 1 and Level 2 Acceptance Criteria were satisfied.

Pressure regulator linearity was recorded at every 2% power increase by comparing pressure regubtor output (E t.) to MWe and turbine first-stage pressure.

Regulator output remained linear.

6.2.9 Test (20)- Feedwater System

Purpose:

To verify the Feedwater Control System has been adjusted to provide acceptable reactor water level control at extended power uprate conditions. Section 6.1.12 discusses the five objectives of the original startup test and identifies the tests that were not be repeated for extended power uprate.

Description:

The Feedwater Control System was modified for extended power uprate to ensure the Condensate and Feedwater System can provide a reliable steady-state supply of feedwater at the new licensed power level, as well as maintain the ability to deliver an additional 5% floiv for analyzed transients. Proper operation of the Feedwater Control System was demonstrated via functional testing of the design modification. Functional testing of the modified controls was performed in accordance with Special Purpose Procedure 17SP-12299-PK-1-IS (DCR 97-051 Dyn unic FT). Single RFP capacity was demonstrated during the performance of Special Purpose Procedure 03SP-030199-SA-1-IS, RFP Capability Test.

Performance of these tests was integrated into the power ascension testing for extended power uprate.

The reactor feedpump turbine (RFPT) electrical stops were increased slightly prior to startup to compensate for extended power uprate operation on higher flow control (rod) lines.

1. Steo Changes Small step changes in reactor water level (2 to 5 in.) were inserted to evaluate level control stability and any oscillatory response. Single-pump tests were conducted at lower power (~ 35% power), and dual-pump tests were performed at - 60% and 95% of the new licensed power level.

HL-5808 E-18

} . .

Enclosure Edwin I. Hatch Nuclear Plant - Unit I g- _ Extended Power Uprate Startup Test Report for Cycle 19 Acceptance l Cnteria Level /: Level control system-related variables contain oscillatory modes of l response. In these cases, the decay ratio for each controlled mode of response is 5 0.25.

Level 2: None.

Respits: Feedwater stability testing was performed at power levels of ~ 35%, ~ 60%, and

- 95%. Both 2-in. and 5-in. positive and negative level setpoint changes were input, and system response was monitored. These step changes were performed in both single-element and three-element control. System response was not oscillatory and showed no signs of divergence. All Acceptance Criteria related to system stability were satisfied.

11. RFP Capacity The capacity of one RFP was verified during startup to determine the maximum power level at which one RFP can maintain RPV water level.

The purpose of this test is to help determine if one RFP, in conjunction with a Reactor Recirculation System runback, can maintain RPV water level above the low RPV water level scram setpoint in the event of an RFPT trip.

Acceptance Criteria: Level l: None.

Level 2: RPV water level, RFPT speed and vibration, and RFP suction pressure remain within the limits specified below.

l Results: The' test was terminated at 67.7% the new licensed power level. Key parameters l collected during this test are tabulated below.

Key Parameter Results Parameter Parameter Parameter Value Limit Reactor thermal power (MWt) 1867 NA RPV water level (in.) 38.74 2 34  ;

RFPT speed (rpm) 5722 55800 ,

i RFP suction pressure (psig) 321.6 2250 RFPT vibration (mils) 1.81 < 4.5  !

l r

HL-5808 E-19 i

Enclosure Edwin I. Ilatch Nuclear Plant - Unit 1 Extended Power Uprate Startup Test Report for Cycle 19 6.2.10 Test (29)- Recirculation MG Set Speed Control Purpose To perform a calibration of the installed Recirculation System flow instrumentation, including specific signals to the plant process computer.

Description:

At operating conditions that allow the Recirculation System to operate at the speeds required for rated flow at 100% uprated power, thejet pump flow instrumentation was adjusted to provide correct flow indication based upon jet pump flow. The total core flow signal to the process computer was calibrated to accurately read the total core flow. This recalibration of the Recirculation System was performed in accordance with Procedure 57CP-CAL-271-IS, Core Flow Measurement. The recirculation pump stops were adjusted, as required.

Acceptance Criteria: Level 1: Per Procedure 57CP-CAL-271-IS.

Level 2: None.

Results Core flow calibration was performed per site procedures. Data were collected.

Core flow calculations were performed, and the current M-ratios were determined.

Jet pump flow summer amplifier gain adjustmcat factors were calculated and evaluated for reasonableness. Required adjustments were made in accordance ,

with site procedures. All Acceptance Criteria were met.

Existing instrumentation associated with the recirculation pumps (e.g.,

recirculation pump motor vibration alarms) were monitored, and no indications of high vibration were observed.

6.3 kiditional Tests l

6.3.1 Steady-State Data Collection

Purpose:

To obtain steady-state data ofimportant plant parameters during startup.

Description:

The selected data taken at power levels greater than the previous maximum licensed power level were extrapolated to predict conditions at 100% of the new licensed power level.

Results: Data were collected for over 100 plant parameters at each Test Condition. The data tracked very well. Extrapolations were made for various instruments recording turbine first-stage pressure, total reactor steam flow, condensate booster pump suction, RFP suction, reactor feedwater temperatures, and TCV positions.

HL-5808 E-20

Enclosure

( j l Edwin 1. Ilatch Nuclear Plant - Unit 1 l

l Extended Power Uprate Startup Test Report for Cycle 19 '

i At the final test condition (Test Condition 7), reactor steam dome pressure was 1035 psig, and turbine throttle pressure was 985 psig. The steamline pressure drop closely matched pre-test analyzed conditions.

i 6.3.2 Thermal Performance

Purpose:

To obtain steady-state data on themial performance when the unit reaches original 100% of power.

Description:

Thermal performance data were collected at steady-state conditions at up to 100%

of the new licensed power level. The thermal performance data were collected in accordance with special purpose procedures. This test was designed to baseline the thermal perfomtance of Unit I at uprated conditions and determine the gross / net generator electrical output change that occurs as a result of implementing extended power uprate. No Acceptance Criteria apply to this test.

Results: The test results were corrected to a constant condenser pressure of approximately 3.5 in. IlG A to allow a consistent comparison of the tests with the design heat balance. The corrected unit load increase from the initial uprate to the extended power rate is - 60 MWe. The electrical output at the maximum tested power level was ~ 911 MWe.

6.3.3 Water Level Measurement Purnose: To check the wide- and narrow-range RPV water level instrumentation. j

Description:

A channel check of various water level instruments was performed at all Test Conditions.

l 4

Acceptance 1 Criteria: Level 1: None. j 1

Level 2: The acceptance criteria of procedure 34SV-SUV-019-IS have been  !

met. ,

I Results: The narrow-range and wide-range indicators were in agreement for all Test t Conditions performed. l t

l t

i

{

IIL-5808 E-21

. . 1 Enclosure Edwin 1. Hatch Nuclear Plant - Unit i Extended Power Uprate Startup Test Report for Cycle 19 TABLE 1 UNIT I FSAR SECTION 13.6 TESTS (SHEET 1 OF 2)

Required for FSAR Test Extended Power No. Test Uprate 1 Chemical and Radiochemical Yes(')

2 Radiation Measurements Yes(*)

3 Fuel Loading No 4 Shutdown Margin Yes(')

5 Control Rod Drive Yes(*)

6 SRM Response and Control Rod Sequence No 7 1RM Performance No 8 LPRM Calibration Yes(*)

9 APRM Calibration ,

Yes(')

10 Process Computer No 11 Reactor Core Isolation Cooling System No 12 High Pressure Coolant injection System No 13 Selected Process Temperatures No 14 System Expansion Nc 15 Core Power Distribution No 16 Core Performance Yes(')

17 Steam Production No 18 Flux Response to Rods No 19 Pressure Regulator Yes*)

20 Feedwater System Yes*)

21 Bypass Valves No 22 Main Steam isolation Valves No 23 Safety Relief Valves No 24 Turbine Trip and Generator Load Rejection No 25 Shutdown from Outside the MCR No HL-5808 E-22

Enclosure Edwin I. Hatch Nuclear Plant - Unit 1 Extended Power Uprate Startup Test Report for Cycle 19 TABLEI UNIT 1 FSAR SECTION 13.6 TESTS (SHEET 2 0F 2)

Required for FSAR Test Extended Power No. Test Uprate 26 Flow Control No 27 Recirculation System No 28 Loss ofTurbme-Generator and Offsite Power No 29 Recirculation MG Set Speed Control . YesN 30 Vibration Measurements No 3i Main TSV Surveillance Test No 32 Recirculation and Jet Pump Instrument Calibration No 33 RWC System No 34 RHR System No 35 Drywell Atmosphere Cooling System No 36 Cooling Water Systems No

a. Credit for existing procedures was taken.

b. During the original startup test program, this test was divided into several subtests to satisfy all criteria. Only some of the original subtests were required for extended power uprate testing.

HL-5808 E-23 mn ._____m__._ m

Enclosure Edwin I. liatch Nuclear Plant - Unit 1 Extended Power Uprate Startup Test Report for Cycle 19 TABLE 2 TEST CONDITIONS Power Test Level Condition (%) MWt 1 88 2436 2 92.6 2558 3 95 2625 4 97.2 2686 5 98 2708 6 99 2735 7 100 2763 IIL-5808 E-24

Enclosure Edwin 1. Hatch Nuclear Plant - Unit i Extended Power Uprate Startup Test Report for Cycle 19 TABLE 3 TESTS PERFORMED FOR EXTENDED POWER UPRATE Test Conditions FSAR Test No. Test <1 1 2 3 4 5 6 7 1 Chemical and Radiochemical x x x x x x 2 Radiation Measurements x x x x x x 4- Shutdown Margin x 5 Control Rod Drive x 8 LPRM Calibration x x 9 APRM Calibration x x x x x 16 Core Performance x x x x x x x 19 Pressure Regulator x x 20 Feedwater System x x 29 Recire MG Set Speed Control x x N/A Thermal Performance x x x N/A Steady-State Data Collection x x x x x x x N/A Water Level Measurement x x x x x x x HL-5808 E-25 L. .

Enclosure Edwin 1. Hatch Nuclear Plant - Unit 1 Extended Power Uprate Startup Test Report for Cycle 19 TABLE 4 PRESSURE REGULATOR "A" STEP CHANGE RESULTS Acceptance Criteria Pressure Lvl 1 - Decay Ratio 1" Stage Steam Flux Press Step s1 Pressure Flow Scram Scram Power Change Lvl 2 - Decay Ratio Resp. Time Variation Margin Margin Level (psi) s 0.25 s 10 sec 0.5% 27.5% 210 psig

-3 =0 <2 0.2 23.I 111.75

+3 =0 <2 0.2 22 111.6 74.5 %

-6 =0 <2 0.2 24.6 113.03

+6 =0 <2 0.2 20.7 113.03

-3 =0 <2 0.26 20.8 45.2

+3 =0 <2 0.26 20.1 45.2 84.8 %

-6 =0 <3 0.26 21.1 45.2

+6 =0 <3 0.26 18.6 44.5

-3 =0 <2 0.34 11.3 46.5

+3 =0 <2 0.34 9.9 46.3 95 %

-6 0.040 <3 0.34 10.7 46.3

+6 =0 <2 0.34 9.1 45.9 ,

1 1

HL-5808 E-26 l

f .- .

Enclosure

. Edwin 1. Hatch Nuclear Plant - Unit !

, Extended Power Uprate Startup Test Report for Cycle 19 TABLE 5 PRESSURE REGULATOR "B" STEP CHANGE RESULTS Acceptance Criteria Pressure Lvl 1 - Decay Ratio 1" Stage Steam Flux Press Step s1 Pressure Flow Scram Scram Power Change Lvl 2 - Decay Ratio Resp. Time Variation Margin Margin l Level (psi) s 0.25 s 10 see 1 0.5 % 27.5% 210 psig

l. -3 =0 <3 0.2 24.3 113.76

+3 =0 <3 0.2 24.2 113.39 74.5% .

-6 =0 <3 0.2 24.9 113.94

+6 =0 <3 0.2 22.6 113.58

-3 =0 <2 0.26 20.7 45.6

+3 =0 <2 0.26 20.4 47.9 84.8 %

-6 =0 <2 ,

0.26 21.1 45.6

+6 =0 <2 0.26 18.9 45.4

-3 =0 <2 0.34 11.7 46.5

+3 =0 <2 0.34 9.6 45.9 95 %

-6 =0 <3 0.34 11.3 46.5

+6. < 0.I <2.

0.34 9.1 46.1

)

i I

I HL-5808 E-27 i ..

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FIGURE 1 UNIT 1 POWER / FLOW MAP HL-5808 E-28

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