ML20100P104
| ML20100P104 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/04/1996 |
| From: | Brown H, Mcelroy S GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20100P094 | List: |
| References | |
| NUDOCS 9603110046 | |
| Download: ML20100P104 (39) | |
Text
T EDWIN I. HATCH NUCLEAR PLANT UNIT 2 i l POWER UPRATE STARTUP TEST REPORT l for !
CYCLE 13 i \
e Prepared by: 8I// Nfm Date: 9/4/9la Power Uprate Project Mdnager /
Reviewed by: _/ Date: 3- Y ' %
Southern Company Services Engineering 9603110046 960304 PDR ADOCK 05000366 P PDR
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report 1 for l Cycle 13 j l
Table of Contents 1
1 Section Eage l 1.0 Executive Summary 1 2.0 Purpose 2 3.0 Program Description 3 4.0 Acceptance Criteria 4 l 5.0 Power Uprate Startup Test Program Summary 5 6.0 Testing Requirements 6 i
6.1 FSAR Supplement 14B Tests Not Required l for Power Uprate 6 i
6.2 FSAR Supplement 14B Tests Required i for Power Uprate 15 Tables 1 Unit 2 FSAR Supplement 14B Tests 33 2 Test Conditions 35 i
3 Tests Performed for Power Uprate 36 l Figures i
1 Power / Flow Map 37 l i
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Edwin I. Hatch Nuclear Plant - Unit 2 l- Power Uprate Startup Test Report for Cycle 13 1.0 EXECUTIVE
SUMMARY
l The Plant Hatch Unit 2 Power Uprate Startup Test Report is submitted to the Nuclear Regulatory Commission (NRC) in accordance with regulatory ;
commitments formerly contained in Unit 2 Technical Specification 6.9. The Technical Specifications requirements are in the process of being relocated to the Plant Hatch Unit 2 Final Safety Analysis Report (FSAR). The report summarizes the startup testing performed on Unit 2 following implementation ofpower uprate during the twelfth refueling outage. Power uprate was implemented in accordance i with Amendment No.138 of Facility Operating License No. NPF-5. (Unit I will l be uprated upon completion of the next refueling outage currently scheduled for Spring 1996.)
The result of power uprate is an increase in reactor power equal to 5% of the original rated thermal power. All testing specified in Supplement 14B of the l
Unit 2 FSAR was addressed and evaluated for applicability to this increased licensed power rating.
The Reactor Mode Switch was placed in the Startup position on November 18, 1995. The final synchronization to the grid was performed on November 21, I 1995, marking the official end to the Unit 2 refueling outage. The new 100%
power (2558 MWt/860 MWe) was first achieved on December 3,1995. .All required power uprate startup tests were completed by December 15,1995.
To successfully achieve the uprated power level, six Special Purpose Procedures were written and implemented in combination with various Surveillance Test i
procedures described in this report. No unusual online adjustments were required l for the following plant systems: Electrohydraulic Control (EHC) - Pressure Regulation, Feedwater, Recirculation, Reactor Core Isolation Cooling (RCIC),
and High Pressure Coolant Injection (HPCI). All systems performed in a stable manner during both plant startup and transient testing. The unit is operating i satisfactorily at power uprated conditions. j I
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 2.0 PURPOSE The Plant Hatch Unit 2 Power Uprate Startup Test Report summarizes the testing performed on Unit 2 following the implementation of power uprate which resulted in an increase in reactor power equal to 5% of the original rated thermal power.
All testing specified in Supplement 14B of the Unit 2 FSAR was addressed and evaluated for applicability to the increased licensed power rating. Each test performed for power uprate is described in Section 6.0. This report is submitted in accordance with regulatory requirements.
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Eowin I. Hctch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 3.0 PROGRAM DESCRIPTION The power uprate startup testing requirements were developed primarily from the review of Supplement 14B of the Unit 2 FSAR, Section 10.3 of the General Electric (GE) Power Uprate Safety Analysis Report for Edwin I. Hatch Nuclear Plant Units 1 and 2, and the GE Uprate Test Program Recommendations. The testing was conducted following the Unit 2 twelfth refueling outage. The results of this testing verified the unit's ability to operate at the uprated power level.
Where possible, testing took credit for existing surveillance procedures. Table I lists the FSAR Supplement 14B startup tests and delineates the testing performed for power uprate.
The majority of testing falls within the following categories:
- 1. Verification the control systems (i.e., Feedwater, EHC - Pressure Regulation, and Recirculation) are stable at power uprate conditions.
- 2. Verification the high pressure injection systems (i.e., RCIC and HPCI) operate acceptably at uprated pressures.
- 3. Collection of data for comparison to original plant rated conditions (i.e.,
radiation surveys, thermal performance, and plant steady-state data).
Table 2 presents the Test Conditions at which startup testing was performed.
Reactor core flow could 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 exceeding the old rated power level of 2436 MWt, the General Manager's approval was required.
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 4.0 ACCEPTANCE CRITERIA Levell Varlable or Criteria: Data trend, singular value, or information which !
relates to Technical Specifications margin and/or plant design in such a manner that requires strict observance.
I 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.
l Leve/ 2 Variable or Criteria: Data trend, singular value, or information relative to system or equipment performance which does not fall under the definition of 1 Level I critena. l
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Level 2 criteria do not constitute a test failure or acceptance; they serve as i information only.
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i Edwin I. Hstch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 i
5.0 POWER UPRATE STARTUP TEST PROGRAM
SUMMARY
The test program began when the Mode Switch was placed in Startup on November 18,1995, and ended with all required Power Uprate Startup Tests complete on December 15,1995. The unit was synchronized to the grid on November 21,1995, marking the official end to the Unit 2 twelfth refueling outage. The new uprated 100% power (2558 MWt) was first achieved on December 3,1995.
i The unit operates satisfactorily at the uprated conditions. No unanticipated online
! adjustments were required to control systems for the following: EHC - Pressure Regulation, Feedwater, Recirculation, RCIC, or HPCI Systems. All systems l performed in a stable menner.
l l Data collected at uprated conditions showed that the 5% increase in reactor power has little, if any, effect on reactor water chemistry and radiological conditions throughout the plant.
All Power Uprate Startup Tests were performed satisfactorily during startup from
! the twelfth refueling outage. Table 3 identifies all the required power uprate startup tests and the Test Conditions in which each test was performed. No Level 1 test failures occurred. One Level 2 criterion associated with pressure regulator testing was not achieved. However, engineering evaluations determined the performance was acceptable.
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 6.0 TESTING REQUIREMENTS Each of the tests discussed in Unit 2 FSAR Supplement 14B was evaluated for applicability to power uprate. Throughout the following discussion, the test numbers and titles, and for:nat are consistent with the FSAR.
1 Section 6.1 identifies each Supplement 14B test not required to be performed for j power uprate. The purpose of the test and the rationale for exempting the test from the power rate program are discussed.
Section 6.2 identifies each test required to be performed for the power uprate. ;
The purpose of the test, a description of the test, and the test results are included.
l l Table 1 identifies all the Supplement 14B tests and their applicability to power uprate. Table 2 lists the five Test Conditions and the associated uprate power level. Table 3 lists the Supplement 14B tests performed for power uprate and the Test Condition (s) for each test. Note that many surveillance tests similar to the original Chapter 14 FSAR tests are performed periodically, often during each startup. Therefore, the power uprate test program took credit for many existing plant procedures.
6.1 FSAR Supplement 14B Tests Not Reauired for Power U.P.ratt ;
i 6.1.1 Test 14B.3 - Fuel Loading !
This test demonstrates the ability to safely and efficiently load fuel to the full core size Fuel loading is performed during every refueling outage in accordance with I site procedures. Power uprate has no impact on this evolution; therefore, no additional testing was required for power uprate 6.1.2 Test 14B.6 - Source Range Monitor Performance and Control Rod Sequence The sou'rce range monitor (SRM) portion of this test demonstrates that the operational sources, SRM instrumentation, and rod withdrawal sequences provide adequate information to the operator during startup. Technical Specifications and l plant procedures ensure proper SRM response during startup. This portion of Test 14B.6 was not repeated for power uprate.
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. Edwin I. Hatch Nuclear Plant - Unit 2 i Power Uprate Startup Test Report for Cycle 13 ,
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The control rod sequence portion of Test 14B.6 demonstrates the ability to
- achieve, in a safe and efficient manner, criticality for each of the specified withdrawal sequences. The effect of rod motion on reactor power at various !
operating conditions is also determined. The manner in which criticality is achieved is not changed by power uprate. The current withdrawal sequence is I performed in accordance with Banked Position Withdrawal Sequence. The rod pattems for intermediate power levels up to uprated power are evaluated using a I three-dimensional simulator code. Performance of this test was not required for power uprate.
6.1.3 . Test 148.7 - Rod Sequence Exchange l )
l This test demonstrates the ability to perform a representative sequence exchange
! of the control rod pattern at a significant power level. Power uprate does not change the manner or methods used for sequence exchanges; thus, this test was ;
not repeated for power uprate.
I 6.1.4 Test 14B.9 - Intermediate Range Monitoring Performance I This test ensures the ability to adjust the intermediate range monitors (IRMs) to obtain optimum overlap with the SRMs and average power range monitors (APRMs). Technical Specifications and plant procedures ensure proper IRM response during startup. This test was not repeated for power uprate. 1
( 6.1.5 Test 14B.12 - Process Computer This test verifies the performance of the process computer under plant operating conditions. The functions of the process computer were not affected by power uprate, although some input variables required modification. This test was not required for power uprate.
6.1.6 Test 14B.15 - Selected Process Temperatures I
This test establishes the minimum recirculation pump speed needed to maintain l water temperature in the bottom head of the reactor vessel within 145'F of reactor j coolant saturation temperature determined by reactor pressure. This test assures l
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i Edwin I. Hatch Nuclear Plant - Unit 2 i Power Uprate Startup Test Report for Cycle 13 l I
that the measured bottom head drain line thermocouple is adequate to measure the bottom head coolant temperature during normal operations. Temperature stratification limits are defined in the Technical Specifications. This test was not required for power uprate. i l
6.1.7 Test 14B.16 - System Expansion This test verifies that reactor drywell piping and major equipraent are unrestrained with regard to thermal expansion. An analysis for power uprated conditions i indicated that the piping systems were acceptable for power uprate; therefore, further testing was not required.
6.1.8 Test 14B.17 - Core Power Distribution 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 symmetry.
Power uprate did not significantly impact these parameters. TIP operation was not affected.
6.1.9 Test 14B.19 - Steam Production This test demonstrates the ability to operate continuously at rated reactor power, j demonstrating that the Nuclear Steam Supply System (NSSS) provides steam at a j sufficient rate and quality. This is the initial warranty run which is not applicable .
to power uprate.
6.1.10 Test 14B.20 - Core Power - Void Mode Test j This startup test demonstrates stability in the power reactivity loop with increasing reactor power and determines the effect of control rod movement on . l reactor stability.
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 power uprate.
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! 4 Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Routine operation in the high power / low flow comer of the power-to-flow map is -
no longer permitted per NRC-approved Interim Corrective Actions for thermal hydraulic stability. I i
6.1.11 Test 14B.22 - Feedwater Control System j
. The five objectives of this startup test are to:
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- 1. Demonstrate reactor water level control.
- 2. Evaluate and adjust feedwater controls.
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- 3. Dernonstrate the capability of the automatic flow runback feature to prevent a low water level scram following a single feedwater pump trip.
. 4. Demonstrate adequate response to feedwater heater loss.
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- 5. Demonstrate general reactor response to inlet subcooling chai ges.
During initial startup, these objectives were demonstrated through the performance of different tests. The tests performed for power uprate are included in Section 6.2.12. The tests that were not performed for power uprate are as follows:
Loss of Feedwater Heating (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 which causes isolation of one or more feedwater heaters. For Unit 2, the limiting equipment failure results in a 105"F decrease in final feedwater temperature if the LOFH occurred at 2436 MWt (old rated power).
Plant-specific transient analyses from previous cycles show acceptable response relative to fuel thermal limits; i.e., Minimum Critical Power Ratio (MCPR)and fuel overpower.
For power uprate, a 107 F decrease in feedwater temperature could result if the same equipment malfunction occurred. (The change in feedwater j' temperature is due to the higher initial feedwater temperature at power uprate conditions.) The LOFH transient was reanalyzed for power uprate, and fuel thermal limits were acceptable. Therefore, the LOFH test was not required for power uprate.
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Single Reactor Feedwater Pumn (RFP) Trip This initial startup test verifies the capability of the automatic recirculation pump runback to prevent a low water level scram following a single RFP trip.
' The only impact of power uprate on this design feature is that power uprate allows operation on a slightly higher flow control (rod) line. Therefore, the core power level may be slightly higher (< 5%) following the recirculation 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 i verified to be larger than required for power uprate conditions. Therefore, l
tripping a RFP at high power was not necessary for power uprate.
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6.1.12 Test 14B.23 - Turbine Valve Surveillance j I
This test demonstrates the ability of the pressure regulator to minimize !
disturbances to the reactor when the turbine stop or control valves are closed.
This test also demonstrates that the turbine valves can be functionally tested at or near rated power without causing a scram.
1 Plant Hatch has years of experience testing individual stop and control valves. j During power uprate startup, the valves were tested, using existing site I procedures, at power levels and pressures where experience shows no problems !
occur. If GPC optimizes power levels for stop and control valve testing, the work l
will be done at a later date. Therefore, this startup test was not performed for power uprate.
6.1.13 Test 14B.24 - Main Steam Isolation Valves ,
The three objectives of this test are to:
- 1. Functionally check the Main Steam Isolation Valves (MSIVs) for proper operation at selected power levels.
- 2. Determine the reactor transient behavior during and following simultaneous full closure of all MSIVs and following closure of one valve.
- 3. Determine MSIV closure times.
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 i
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Large transient testing performed at high power during the initial startup demonstrated the adequacy of protection for these large transients. Analysis shows that should these transients occur at 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. i MSIVs will continue to be surveillance tested per existing site procedures. ;
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6.1.14 Test 14B.25 - Safety Relief Valves '
This test verifies proper operation of dual-purpose safety relief valves (SRVs), ;
including determination of capacity and leaktightness verification following !
operation. SRV capacity was not affected by power uprate. SRV setpoints were increased 3% for power uprate. During the outage, the new setpoints were reset and tested prior to installation. The SRVs were exercised at low power using existing procedures. This startup test, as described in the FSAR, was not l
performed for power uprate.
1 6.1.15 Test 14B.26 - 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. Large transient testing performed at high power levels during the initial startup demonstrated the adequacy of protection for these large transients. Analysis shows that should these transients occur at uprated conditions, the change in unit performance will be small; therefore, testing the unit's response to turbine and generator trips at uprated conditions was not required.
6.1.16 Test 14B.27 - Shutdown from Outside the Main Control Room This test demonstrates the ability to shut down the reactor from normal 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). Power uprate did not alter the capability of the reactor to be shut down from outside the MCR; therefore, this test was not repeated for power uprate.
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 6.1.17 Test 14B.28 - Flow Control This startup test determines the plant response to changes in recirculation flow, and thereby, adjusts the local control loops. Also, the load following capability of the plant is established.
Power uprate does not significantly affect the recirculation flow control system or licensed core flow limits. Therefore, the recirculation flow control startup test was not required for power uprate.
6.1.18 Test 14B.29 - Recirculation System The two objectives of this test are to:
- 1. Determine the transient responses and steady-state conditions following recirculation pump trips and obtain jet pump performance data.
- 2. Verify that no recirculation system cavitation occurred.
The initial startup test determined the transient response during recirculation -
pump trips, flow coastdown, and pump restarts. Power uprate did 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 power uprate was not required.
6.1.19 Test 14B.30 - Loss of Turbine-Generator and Off-Site Power This test demonstrates proper performance of the reactor and the plant electrical equipment and systems during the loss of auxiliary power transient. 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 at uprated conditions was demonstrated during the power ascension to uprate conditions; therefore, this test was not required for power uprate.
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- l Edwin 1. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 s
6.1.20 Test 14B.31 - Drywell Piping Vibration 4
This test verifies the acceptability of the vibration characteristics of the main 4
steam and recirculation piping. Analysis shows that the net impact from power
- uprate would be minimal and was considered negligible. Therefore, this test was not repeated for power uprate.
6.1.21 Test 14B.33 - RWC System This initial startup test demonstrates the specific aspects of the mechanical
- operability of the Reactor Water Cleanup (RWC) System. Detailed evaluations l show the impact of a 5% increase in thermal power causes minor changes in RWC ,
j System operating performance requirements; however, the changes are well within the system's design parameters. No specific RWC testing was required for i power uprate.
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J 6.1.22 Test 14B.34 - RHR System j This test demonstrates the ability of the Residual Heat Removal (RHR) System to:
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- 1. Remove decay heat from the NSSS so that refueling and servicing can be 4
performed.
- 2. Condense steam while the reactor is isolated from the main condenser.
4 i The capability of the RHR System to remove residual and decay heat has been
[ demonstrated many times over the years. Power uprate's effect on system j performance is a small increase in reactor cooldown time; the system will continue to perform acceptably. The steam condensing mode of RHR was
! removed and thus, is not a factor. Based on these factors, the RHR System startup test was not required for power uprate, 6.1.23 Test 14B.35 - Offgas-4 This initial startup test demonstrates the ability of the Offgas System to operate within Technical Specifications limits. Power uprate was determined to have a minimal impact on this system; therefore, no additional testing was required.
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L Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 l
6.1.24 Test 14B.36 - MSIV Leakage Control System This system was removed in 1994.
6.1.25 Test 14B.37 - Hydrogen Recombiners l
l The original startup test took credit for pre-operational testing on the itecombiner L System. The impact of power uprate on system performance was determined to l
be minimal, and, at most, would require earlier manual initiation of the
! recombiners following a large break LOCA. No special testing for power uprate j l was required. I 6.1.26 Test 14B.38 - Primary Containment Cooling System This startup test demonstrates the ability of the Primary Containment Cooling System to maintain drywell temperatures within the temperatures assumed in the safety analysis.
Power uprate was expected to have a minimal impact (1 to 2*) on drywell i temperature. The ability of the cooling system to keep average drywell gas temperature below 135*F has been demonstrated for years. This Technical Specifications requirement was verified at uprated conditions, and no additional testing was required.
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 '
6.2 FSAR Supplement 14B Tests Required for Power Uprate 6.2.1. Test 14B.1 - Chemical and Radiochemical Tests Purnose: Tc determine the effects of power uprate on reactor coolant chemistry,
Description:
Chemical and radiochemical samples were taken in accordance !
, with plant procedures at the original 100% power level s
(95% uprated),98% uprated power level, and 100% uprated power level.
Acceptance Criteria:
Levell: Per Procedure 60AC-HPX-010-0S, " Plant Sampling and Monitoring Program," and the Unit 2 Technical Requirements Manual (TRM).
Level 2: None Results-Procedure 60AC-HPX-010-0S was .r brmed satisfactorily at 95%,98%, and 100% uprated power. All Acceptance Criteria were satisfied.
A hydrogen injection test was performed after power uprate testing was completed. The injection test required operation without hydrogen addition from 2 to 4 weeks after startup. Therefore, chemistry data, as shown below, for power uprate were taken at normal chemistry conditions.
Chemistry Results Actual Data Actual Data Acceptance Parameter (95%) (100%) Criteria Primary Reactor 0.10 0.09 52.0 2 2 2 Coolant Conductivity umhos/cm umhos/cm umhos/cm Primary Reactor Coolant Chloride 0.8 ppb 1.2 ppb $ 200 ppb I
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 6.2.2 Test 14B.2 - Radiation Measurements I
Purpose:
To measure radiation levels at selected locations and power conditions to assure the protection of plant personnel and continual compliance i with the guidance of 10 CFR 20 during plant operation. l
Description:
Radiation levels were measured at various locations in the plant at l uprated power levels of 95,98, and 100% in accordance with plant j procedures.
Acceptance Criteria:
Level 1: Radiation doses of plant origin and occupancy times of personnel in radiation zones are controlled consistent with the guidance on I standards for protection against radiation found in 10 CFR 20. I Level 2: None Results: Radiation surveys were conducted at uprated power levels of 95,98, and 100% in accordance with applicable sections of Departmental !
Instruction DI-RAD-03-1087N, " Survey / Inspection Frequency and Work Scheduling." The radiation data were taken at normal water chemistry conditions. The dose rates were the same as those experienced at the original power levels. No postings were changed as a result of achieving the uprated 100% power level. Radiation dose rates remain within the standards for protection against radiation q outlined in 10 CFR 20.
l 6.2.3 Test 14B.4 - Shutdown Margin
Purpose:
To demonstrate that throughout the fuel cycle, the reactor will be l subcritical with the analytically determined highest worth control rod j capable of being fully withdrawn and all other rods fully inserted.
Ilescription: SDM demonstrations were performed in accordance with Procedure 42CC-ERP-010-0S, " Shutdown Margin Demonstration." The demonstration was performed analytically !
during the Cycle 13 BOC, using an insequence critical control rod with the reactor core in a Xenon-free state. Correction factors were used to adjust to startup conditions.
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Edwin I. Hatch Nuclear Plant - Unit 2 l Power Uprate Startup Test Report for Cycle 13 Acceptance Criteria:
Levell: SDM is > 0.38% A' n + R, as specified in the Technical Specifications and %)cedure 42CC-ERP-010-0S, " Shutdown Margin Determination."
i Level 2: None l Results: For Unit 2 Cycle 13, the required SDM was > 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.
As Unit 2 reached criticality, SDM was calculated in accordance with Procedure 42CC-ERP-_010-0S. Cycle 13 SDM was determined to be 1.997% Ak/k, thus satisfying the Level 1 Acceptance Criteria.
6.2.4 Test 14B.5 - Control Rod Drive
Purpose:
To demonstrate that the control rods meet Technical Specifications requirements for scram times.
Description- Scram Timing of control rods was performed in accordance with
- Procedure 42SV-Cl1-003-0S," Control Rod Scram Testing."
- CRD Timing was performed in accordance with Procedure 34SV-C11-004-2S,"CRD Timing."
Accentance Criteria:
Levell: Per Procedure 42SV-Cl1-003-2S and applicable Technical Specifications.
Level 2: Per Procedure 34SV-C11-004-2S.
Results: Scram Time Testing was performed for selected control rods during either the RPV Leakage Test or below 40% of uprated thermal power during startup. All Level 1 Acceptance Criteria, per Procedure 42SV-Cl1-003-0S," were satisfied. The Scram Time Acceptance Criterion for each control rod shown below is the required scram insertion time from the fully withdrawn position. An individual l
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13
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control rod that fails to meet criteria is declared a " SLOW" rod.
However, all 137 control rods met the Acceptance Criteria.
Scram Time Testing Results Position Inserted from Acceptance Criteria Fully Withdrawn (seconds) 46 0.44 36 1.08 26 1.83 l
06 3.35 l
l CRD Timing data for insertion and withdrawal speeds met the Level 2 l Acceptance Criteria of 38.4 to 57.6 seconds specified in Procedure 34SV-Cl 1-004-2S. For CRDs with an adjusted drive speed, the criteria ranged from 43.2 to 52.8 seconds.
6.2.5 Test 14B.8 . Water Level Measurement Purnose: To check the wide- and narrow-range vessel water level instrumentation.
Description:
A channel check of various water level instruments was performed at all five Test Conditions.
Acceptance Criteria:
l Level 1: None 4
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Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Level 2. Narrow-range water level instruments agree within either 1.5 in of L the average reading. Wide-range indicators agree within 6 in. of I each other.
l Results: The water level indications were acceptable at all five Test Conditions.
I Results at 95% and 100% of uprated power are tabulated below.
Water Level Measurements Test Results Test Results Acceptance Indicator 95 % 100 % Criteria 2C32-R606A,B,C 1.5 in. 1.5 in. 1.5 in. I i
2B21-R604A,B 1.0 in. 1.0 in. 6.0 in.
2B21-R623A,B 5.0 in. 3.0 in. 6.0 in.
6.2.6 Test 14B.10 - Local Power Range Monitor Calibration Purnose: To calibrate the local power range monitors (LPRMs).
Description:
The LPRM channels were calibrated to make the LPRM readings I proportional to the neutron flux in the narrow-narrow water gap at the chamber elevation. This calibration was performed in ;
accordance with Procedure 52SV-C51-005-2S, "LPRM
. Calibration."
Acceptance Criteria:
i Level 1: Per Procedure 52SV-C51-005-2S.
1 Level 2- None Results: Using site procedures, LPRMs were successfully calibrated at 100%
uprated power. Average LPRM Gain Adjustment Factor Values for all operable LPRM channels were within specified limits.
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i Edwin I. IIatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 6.2.7 Test 14B.11 - Average Power Range Monitor Calibration l Purnose: To calibrate the APRMs to actual core thermal power, as determined by a heat balance, o
Description:
Each APRM channel reading was adjusted to be consistent with l
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 Thermal Power."
Accentance Criteria:
1 Level 1: At least two or more APRMs per RPS trip system are calibrated to I rated thermal power. These readings agree with the heat balance !
values within 2%.
Level 2 None Results- APRM gain adjustments were performed at different power levels during the Power Uprate Startup Test Program. Each was completed satisfactorily, and no problems occurred during the tests.
6.2.8 Test 14B.13 - Reactor Core Isohtion Cooling System .
Purnose: To verify proper operation of the RCIC System at the uprated operating pressure and provide baseline data for future surveillance 4 testing. I
Description:
As part of the normal plant startup, Procedure 34SV-E51-004-2S, "RCIC Pump Operability 150 psig Test," was performed to demonstrate adequate control of the turbine and rated flow capability.
Using Procedure 34SV-E51-002-2S,"RCIC Pump Operability," a condensate storage tank (CST) to CST injection was performed at it 920 psig to demonstrate acceptable operation at the lower end of ;
the operating pressure range for power uprate and to provide a - ,
benchmark to which future surveillance tests are compared. .
l At the uprated operating pressure, a Cold Quick Start was perfonned in accordance with Procedure 34SV-E51-002-2S. As 20
j Edwin I. Hatch Nuclear Plant - Unit 2 I Power Uprate Startup Test Report for Cycle 13 part of the analysis of the RCIC quick start at rated conditions, all .
control parameters (e.g., speed and flow) were analyzed for proper !
performance. l l
l Using the HPCI/RCIC Data Acquisition System, proper control l system tuning was verified.
l !
! Acceptance Criteria: l l
Level 1:
- 1. RCIC surveillance procedures are satisfactorily completed. This includes requiring the system to deliver rated flow (400 gpm) at any reactor pressure ,
between 150 psig and rated pressure at power uprate conditions. The system l must deliver rated flow within 45 seconds from the automatic initiation at any reactor pressure > 920 psig.
- 2. The RCIC turbine cannot trip or isolate during auto or manual starts.
Level 2:
l
- p. The barometric condenser is capable of preventing steam leakage to the atmosphere during operation.
- 2. The differential pressure (dP) switches for the steamline isolation are properly calibrated.
Other-
- 1. The transient start first and subsequent speed peaks are not more than 5%
faster than the rated RCIC turbine speed.
- 2. The decay ratio of any RCIC System-related variable is not > 0.25.
Results: The RCIC pump surveillance procedure was performed satisfactorily.
RCIC operability was verified at 150 psig. The pump flow rate was 400 gpm at a turbine speed of 2435 rpm. The time to rated flow was
~ 30 seconds. All Acceptance Criteria were satisfied.
With reactor pressure at ~ 920 psig, the RCIC pump surveillance procedure was performed satisfactorily. The RCIC turbine did not trip; a j rated flow > 400 gpm was achieved with a discharge pressure > 100 psig i
above reactor pressure in < 45 seconds, thus satisfying all Level 1 21
Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 Acceptance Criteria. All Level 2 Acceptance Criteria were satisfied. '
The control system tuning parameter checks also met the Acceptance Criteria.
The RCIC pump surveillance procedure was performed satisfactorily at uprated pressure. A Cold Quick Start was performed. RCIC pmnp flow was 400 gpm at a pressure of 1170 psig. The response time to rated flow was 31.3 seconds, with no perceptible initial speed spike. No tuning was needed; the system ran smoothly. The decay ratio for the speed control loop was zero. All Level 1 and 2 Acceptance Criteria were satisfied.
6.2.9 Test 14B.14 - High Pressure Coolant Injection System Purnose: To verify proper operation of the HPCI System at the uprated operating pressure and provide baseline data for future surveillance testing.
Description:
As part of the normal plant startup, Procedure 34SV-E41-005-2S, "HPCI Pump Operability 165 psig Test," was performed to demonstrate adequate control of the turbine and rated flow capability.
Using Procedure 34SV-E41-002-2S, "HPCI Pump Operability," a CST injection was performed at 2 920 psig to demonstrate acceptable operation at the lower end of the operating pressure range for power uprate and provide a benchmark to which future surveillance tests will be compared.
At the uprated operating pressure, a Cold Quick Start was performed in accordance with Procedure 34SV-E41-002-2S.
Acceptance Criteria:
LestLL
- 1. HPCI surveillance procedures are satisfactorily completed. This includes requiring the system to deliver rated flow (4250 gpm) at any reactor pressure between 165 psig and rated pressure at power uprate conditions. The system must deliver rated flow within 49 seconds from the automatic initiation at any reactor pressure 2 920 psig.
- 2. The HPCI turbine cannot trip or isolate during auto or manual starts.
22
Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 4
Level 2
~ 1. The barometric condenser is capable of preventing steam leakage to the atmosphere during operation.
4-
- 2. The dP switches for the steamline isolation are properly calibrated.
Other-
, 1. The transient start first speed peak is at least 15% (of rated turbine speed) below the overspeed trip. Subsequent speed peaks are not more than 5%
faster than the rated HPCI turbine speed. -
- 2. The decay ratio of any IIPCI System-related variable is not > 0.25.
Results: The HPCI pump surveillance procedure was performed satisfactorily. ,
l A pump flow rate of 4250 gpm was achieved. Turbine speed was 2180 rpm; the turbine did not trip. All Level 1 and Level 2 l
- Acceptance Criteria were satisfied.
j i .
The HPCI pump surveillance was completed satisfactorily at 932 psig.
The following Acceptance Criteria were met: ]
l l
Acceptance Test Results Parameter Criteria Rated Flow 24250 gpm 4250 gpm Pump Discharge Pressure 21135 psig 1185 psig Decay Ratio s 0.25 0.0 Response Time s 49.0 sec 22.0 sec 23
Edwin I. Hitch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 No speed requirements were exceeded. The speed and flow control loops did not require any adjustment. The decay ratio was < 0.25, thereby satisfying all Acceptance Criteria.
The HPCI pump surveillance was performed satisfactorily at 100%
uprated power. A Cold Quick Start was performed in conjunction with a stability (tuning) check. No turbine trip or isolation occurred. The following Acceptance Criteria were satisfied:
Acceptance Parameter Criteria Test Results Rated Flow 2 4250 gpm 4250 gpm Pump Discharge Pressure 21135 psig 1200 psig Decay Ratio $ 0.25 0.0 h
l Response Time s 49.0 seconds 20.5 seconds i I
The transient start peak speed was well below the limit of 4400 rpm !
and subsequent peaks were well below the 4260 rpm limit. All j Acceptance Criteria were met. ;
6.2.10 Test 148.18 - Core Performance Purnose: To evaluate the core performance parameters to assure plant thermal limits are maintained during the ascension to uprated conditions.
Description:
As power is increased, core thermal power was measured at all five Test Conditions up to 100% uprate power, using the current plant methods of monitoring reactor power.
24
Edwin I. Hatch Nuclear Plant - Unit 2 l Power Uprate Startup Test Report for Cycle 13 In accordance with Procedure 34SV-SUV-020-0S," Core Parameter Surveillance," demonstration of fuel thermal margin was l performed at each test condition. Fuel thermal margin was l projected to the next test point to show expected acceptance margin l and was satisfactorily confirmed by the measurements taken at each test point before advancing further.
l Acceptance Criteria:
Level 1-The following thermal limits are < l.000:
- 1. MFLPD (Maximum Fraction of Limiting Power Density)
- 2. MFLCPR (Maximum Fraction of Limiting Critical Power Ratio)
- 3. MAPRAT (Core Maximum Average Planar Linear Heat Generation Rate Fraction)
Level 2-None Results: Thermal limits were continuously monitored during power ascension.
i- The surveillance procedure was performed satisfactorily at each Test Condition, thus meeting all Acceptance Criteria. Results for Test i- Conditions 2 through 5 are as follows:
Uprated Power Level Thermal Limit 90 % 95 % 98 % 100 %
(
- Steady-State Xenon i
25 l
(
Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 6.2.11 Test 148.21 - Pressure Regulator Purnose: 1. To confirm that 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.
, 2. To demonstrate that affected plant parameters are within acceptable limits during pressure regulator-induced transients.
- 3. To verify that variation in incremental regulation is within i acceptable limits (linear). ;
Description:
The steamline pressure transmitters were replaced and functionally tested during the outage. The pressure regulator was tuned and 1 tested prior to startup per the guidance of Service Information l Letter (SIL) 589, " Pressure Regulator Tuning." Electronics were ;
replaced and tested, as necessary, to assure stable turbine control
)- valve operation.
! During startup,3,6, and 10 psi step changes in reactor pressure were simulated, and the resulting transient was 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 performed with pressure regulator "A" in control and second with pressure regulator "B" in control.
This test was performed while on turning gear with the bypass
, valves controlling reactor pressure (~ 25% power), at an
- intermediate power level (65-75%), and at Test Condition 3 (95% power).
Starting at ~ 200 MWe, steam flow, MWe, first-stage pressure, and
, pressure regulator output (E t,) were recorded at every 2% power increase until full power was achieved. The data were plotted to confirm pressure regulation linearity.
Acceptance Criteria:
1 Level 1: The transient response of the turbine inlet (throttle) pressure to any test -
input cannot diverge (decay ratio = < 1). This can be visually verified j by observing that the successive peaks of the same polarity are of 4
equal or decreasing amplitude.
26
Edwin I. Hatch Nuclear Plant - Unit 2
- Power Uprate Startup Test Report for Cycle 13 i
Level 2 1. The decay ratio of the turbine inlet (throttle) pressure is s 0.25, when operating above the minimum core flow of the Master Flow ,
Control range. Below this minimum core flow, the decay ratio - l must be 5 0.50. The decay ratio of each control system should be adjusted to 5 0.25, unless a performance loss involved at higher ;
power levels is identified. -1 i
- 2. The response time from pressure setpoint input until the pressure l e peak of the turbine inlet pressure is s 10 seconds. !
- 3. Pressure control system deadband and delay are small enough that steady-state limit cycles (if any) produce steam flow variations no larger than 0.5 % of rated steam flow.
1
- 4. Peak neutron flux and peak vessel pressure remain below scram settings by 7.5 % and 10 psi, respectively.
Results: Pressure regulator stability testing was performed at uprated power levels of~ 22%,73% and 95% power. Selected data obtained during each Test Condition are summarized in the tables below.
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 except for the Level 2 Acceptance Criterion of a decay ratio 5 0.25 at the 95% power Test Condition.
That is, testing showed that control valve no. 4 was velocity limited when the pressure setpoint step change caused a reduction in system
{
pressure. (A pressure step decrease simulated a rapid increase in l output power demand.) No other Level 1 or Level 2 Acceptance Criteria violatioas occurred. j
, 1 The test results were evaluated and the transient response deemed I acceptable. Pressure regulator step change testing was not performed on the regulator "B" at 95% power.
7 27
% ,%# w . . _ _ -- , . . - c
Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 l
l Pressure Regulator "A" Step Change Data l
l Peak Pressure Pressure Response Peak Steady Power Step Step Change Time Power State Level (+/-) Size (psig) ,
(sec) (%) Cycles 22 % 3 3 4 2.6 24 0 (Turning 6 6 8 3.0 25 0 Gear) 10 10 14 3.0 27 0 3 3 4 1.9 79 0 l 73 % 6 6 7 2.7 80 0 10 10 11 3.4 83 0 3 3 4 5.4 98 2 95 % 6 6 6 5.0 100 2 10 NA NA NA NA NA Pressure Regulator "B" Step Change Data Peak Pressure Pressure Response Peak Steady Power Step Step Change Time Power State Level (+/-) Size (psi) (sec) (%) Cycles 22 % 3 3 4 2.7 23 0 ;
(Turning 6 6 8 2.8 25 0 l Gear) 10 10 13 2.8 28 0 3 3 4 2.0 77 0 73 % 6 6 7 2.8 80 0 10 10 11 3.5 83 0 3 NA NA NA NA NA l 95 % 6 NA NA NA NA NA l 10 NA NA NA NA NA I Pressure regulator linearity was also recorded at every 2% power increase I by comparing pressure regulator output (Et) to MWe and turbine !
first stage pressure. The regulator output remained linear. )
l l l .
28
l' s
- Edwin I. Hatch Nuclear Plant - Unit 2
{ Power Uprate Startup Test Report for Cycle 13 l
T j 6.2.12 Test 14B.22 - Feedwater Control System 2
Puroose: To verify that the Feedwater Control System has been adjusted to i provide acceptable reactor water level control at uprated conditions.
Section 6.1.11 discussed the five objectives of the original startup test and identified the tests that were not be repeated for power uprate.
The description below provides information on the Feedwater System testing performed for power uprate.
i
- The Unit 2 Reactor Feed Pump Turbine (RFPT) speed controls were
{' upgraded to a GE Mark V governor system with speed feedback.
Also, the RFPT electrical stops were increased slightly prior to the
, startup to compensate for power uprate operation on higher flow control (rod) lines. The testing for the upgraded turbine controls was integrated with power uprate testing. Key uprate-related tests include: l j I. Steo Channes Small step changes in 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 ~ 70% power and at Te'st Condition 3.
Level 1 Criteria:
- 1. Level control system-related variables contain oscillatory modes of response. In these cases, the decay ratio for each controlled mode of response is < 0.25. .
- 2. At steady-state generation for the 3/1 element systems, the i input scaling to the mismatch gain is adjusted such that level error due to biased mismatch gain output is within 1in.
- 3. The variation in incremental regulation (feedwater flow demand change divided by actual feedwater flow change for small disturbances) does not exceed a factor of 2 to 1 between feedwater flow demand and feedwater flow.
- 4. The turbine speed regulation variation between the two feed pumps must match within 5% of rated speed.
Level 2 Criteria: None 2 29
L Edwin I. Hatch Nuclear Plant - Unit 2
!- Power Uprate Startup Test Report for Cycle 13 l
Results- Feedwater Stability Testing was performed at uprated power levels of 35%,70%, and 95% Both 2-in. and 5 in. positive and negative level l 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 ofdivergence. No system adjustments were required.
All Acceptance Criteria related to system stability were satisfied.
The level error between single- and three-element level control was verified following stability testing. The level did not change more than l 1 in. on each transfer. All test Acceptance Criteria were satisfactory.
L Data were taken and plotted for both single- and two-pump configurations, and the variation in incremental regulation was 5 2:1 for both conditions.
II. RFP Capacity The capacity of one RFP was verified during startup to determine the maximum power level at which one RFP can maintain reactor vessel water level. The purpose of this test is to help determine if one RFP, in conjunction with a Reactor Recirculation System runback, can maintain water level above the low reactor vessel water level scram setpoint in the event of an RFPT trip.
Level 1 Criteria: None Leve/ 2 Criteria: Vessel water level, RFP turbine speed and j vibration, and RFP suction pressure remain within the limits specified below.
Results The test was terminated at 76% of uprated power. Key parameters collected at this power level are tabulated below.
Parameter Parameter Parameter Value Limit Reactor thermal power (MWt) 1942 NA RPV water level (in.) 39.5 2 34 in.
RFP turbine speed (rpm) 5413- 5 5700 rpm l RFP suction pressure (psig) 399 2 250 psig RFP turbine vibration (mils) 2.0 < 4.5 mils ,
RFP turbine vibration (mils) 1.2 < 4.5 mils i
30
Edwin I. Hatch Nuclear Plant - Unit 2 j Power Uprate Startup Test Report for Cycle 13 l
6.2.13 Test 14B.32 - Recirculation System Flow Calibration Puroose: To perform a 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% uprated power, thejet pump flow instrumentation was adjusted to provide correct flow indication based onjet 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-271-2S,
" Core Flow Measurement." The recirculation pump stops were ,
adjusted, as required. !
Acceptance Criteria:
Level / Criteria Per Procedure 57CP-CAL-271-2S.
Level 2 Criteria: None.
Results' Core flow calibration was performed per site procedures. Data were .
collected. Core flow calculations were performed, and current the M-ratios were determined. Jet Pump Flow Summer Amplifier Gain Adjustment 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.
31
1 Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 i
6.2.14 Steady-State Data Collection
)
l
Purpose:
To obtain steady-state data ofimportant plant parameters during !
startup at Test Conditions 1 through 5. The selected data taken at power levels > 100% were extrapolated to predict conditions at 100% uprated power.
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, reactor feedwater temperatures, and turbine control valve positions.
During startup and ascension to old rated power, EHC pressure was set at 920 psig. As reactor power increased above 2436 MWt, fine adjustments to pressure set were made to increase reactor pressure and turbine throttle pressure, allowing for a complete set of data at 2436 MWt prior to ascension to 2558 MWt.
At Test Condition 5, reactor steam dome pressure was 1035 psig, and turbine throttle pressure was 985 psig. The steamline pressure drop closely matched pre-test conditions.
6.2.15 Thermal Performance Puroose: To obtain steady-state data on thermal performance when the unit reached original 100% power (2436 MWt). ' The same data were collected at steady-: tate conditions at the uprated power level of 100% (2558 MWt).
Results The thermal perfor marce data were collected in accordance with special purpose procedures. This test was designed to baseline the thermal performance of Unit 2 at uprated conditions and determine the gross / net generator electrical output change which occurs as a result ofimplementing power uprate. No Acceptance Criteria apply to this test.
32
I Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 1
i TABLE 1 UNIT 2 FSAR SUPPLEMENT 14B TESTS (SHEET 1 OF 2) l Required for
, FSAR Test No. Test Power Uprate .
1 Chemical and Radiochemical Yes(*)
2 Radiation Measurements Yes(')
3 Fuel Loading No i 4 Shutdown Margin Yes(*)
5 Control Rod Drive Yes(*)
6 SRM Performance and Control Rod Sequence No 7 Rod Sequence Exchange No 8 Water Level Measurement Yes(*)
9 IRM Performance No 10 LPRM Calibration Yes(')
11 APRM Calibration Yes(')
12 Process Computer No 13 Reactor Core Isolation Cooling Yes(')
14 High Pressure Coolant Injection Yes(')
15 Selected Process Temperatures No 16 System Expansion No 17 Core Power Distribution No 18 Core Performance Yes(')
19 Steam Production No 20 Core Power Void Mode No 21 Pressure Regulator Yes(*)
22 Feedwater Control System Yes(*)
23 Turbine Valve Surveillance No 24 Main Steam Isolation Valves No 25 Safety Relief Valves No 26 Turbine Trip and Generator Load Rejection No 27 Shutdown From Outside the MCR No 28 Flow Control No 29 Recirculation System No 30 Loss of Turbine Generator and Offsite Power No 31 Drywell Piping Vibration No 33 i
i Edwin I. Hatch Nuclear Plant - Unit 2 l Power Uprate Startup Test Report for Cycle 13 TABLE 1 UNIT 2 FSAR SUPPLEMENT 14B TESTS (SHEET 2 OF 2)
Required for FSAR Test No. Test Power Uprate 32 Recirculation System Flow Calibration Yes*
t 33 RWC System No 34 RHR System No l 35 Offgas System No l 36 MSIV Leakage Control No 37 Hydrogen Recombiners No 38 Primary Containment Cooling System No
- a. Credit for existing procedures was used.
- 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 power uprate testing.
l l
l I
34 l
1 l
l Edwin I. Hatch Nuclear Plant - Unit 2 l
Power Uprate Stcrtup Test Report for Cycle 13 l i l
' \
TABLE 2 '
TEST CONDITIONS 1
l l
Test Condition Uorated Power Level Ucrated MWt 1 1 .5 85 % $2174 2 90 % 2302 )
l 3 95% (Note 1) 2436 (old rated) l 4 98 % 2506 5 100% (Note 2) 2558 l
I Notes:
- 1. Original 100% power is equal to 95.2% uprated power.
1
- 2. 100% uprated power is equal to 2558 MWt. !
l l
l l
I I ,
35
!, Edwin I. Hatch Nuclear Plant - Unit 2 Power Uprate Startup Test Report for Cycle 13 l l
l TABLE 3 TESTS PERFORMED FOR POWER UPRATE
Test Condition--------------
FSAR Test No. Test <1 1 2 3 4 5 1 Chemical and Radiochemical x x x 2 Radiation Measurements x x x 4 Shutdown Margin x 5 Control Rod Drive x 8 Water Level Measurement x x x x x ;
10 LPRM Calibration x 11 APRM Calibration x x x 13 RCIC (150 psig) x 13 RCIC (> 920 psig) x 13 RCIC Cold Quick Start x 14 HPCI (165 psig) x 14 HPCI (> 920 psig) x 14 HPCI Cold Quick Start x 18 Core Performance x x x x x 21 Pressure Regulator x x 32 Recirc System Flow Calibration x N/A Thermal Performance x x ;
N/A Steady-State Data Collection x x x x x 36
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