ML20112C169

Startup Rept Cycle 7

ML20112C169
Person / Time
Site:	Limerick
Issue date:	05/17/1996
From:	Gallagher M, Gardner P, Walter MacFarland PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9605240251
Download: ML20112C169 (46)

Text

W11ttr G. MxcFarland, IV, P.E.

Vce President A Limerick Generatrig Station v

PECO NUCLEAR eew emeev c-wey PO Box 2300 A UNir or PECO ENERC) Sanatoga. PA 19464-0920 610 718 3000 i Fax 610 718 3006 Pager 1800 672 2285 #8320 l

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T.S. 6.9.1.1 May 17, 1996 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC '20555

SUBJECT:

Unit 1 Startup Test Report

. Attached is the Startup Test Report which summarizes the r,tartup testing performed on Limerick Generating Station Unit 1 following implementation of Power Rerate during the sixth Unit 1 Refueling Outage. This startup report is being submitted in accordance with the requirements of Technical Specifications Section 6.9.1.1.

If you have any questions please contact Peter Gardner at (610) 718-3569.

Singerely,

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DMS:cah cc: T. T. Martin, Administrator Region I, USNRC N. S. Perry, USimC Senior Resident Inspector, LGS 24007G  !

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PECO NUCLEAR Umerick Generating Station Unit 1 Startup Report cycle 7 i

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i Preparation Directed By:

M. P. Gallagher, Director - Site Engineering i

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Prepared By:

j P. A. Gardner, 'Amactor Engineer i

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s PECO NUCLEAR Limerick Generating Station S

Unit 1 Startup Report Cycle 7 Preparation Directed By:

M. P. Gallagher, Director - Site Engineering Prepared By:

P. A. Gardner, Reactor Engineer l

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Limerick Generating Station Unit 1 Rerate Startup Test Report Page 1 of 43 PAG:mbc TABLE OF CONTENTS Section Title Page 1.0 Exe cu t.1. '-: Summary 2 2.0 Purpose 3 3.0 Program Description 3 4.0 Acceptance Criteria 4 5.0 Rerate Startup Test Program Summary 5 6.0 Testing Requirements 6 6.1 UFSAR Chapter 14.2 Tests Not Required For 6 Power Rerate 6.2 UFSAR Chapter 14.2 Tests Recommended For 12 Power Rerate TABLES 1 UFSAR Chapter 14.2 Tests 39 2 Test Conditions 40 3 Tests to be Performed for Power Rerate 41 FIGURES 1 Power / Flow Map 42 2 RCIC Acceptance Criteria Curves for capacity and Actuation Time 43

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Limerick Gancrating Station Unit 1 Rerate Startup Test Report Page 2 of 43 PAG:mbc LIMERICK GENERATING STATION l POWER RERATE I STARTUP TEST PROGRAM PIJLN 1.0 EXECUTIVE

SUMMARY

This Startup Test Report is submitted to the Nuclear Regulatory Commission (NRC) in accordance with the ,

requirements of Limerick Generating Station (LGS) Technical Specification 6.9.1.1. The report summarizes the startup testing performed on LGS Unit 1 following implementation of Power Rerate during the 1R06 Refueling Outage. Power Rerate

.was implemented in accordance with Amendment of the Facility Operating License No. NPF-39 and Operating License Change Request No. 93-24-0 The result of Power Rerate is an increase in reactor power '

equal to 5% of the original rated thermal power. All testing identified within the LGS Updated Final Safety Analysis Report (UFSAR) Chapter 14.2 was addressed and evaluated for applicability to this increased licensed power rating as required by Technical Specifications.

The Reactor Mode Switch was placed in the Startup position on February 28, 1996. The final synchronization to the grid was performed on March 01, 1996, marking the official end to the Unit 1 sixth refueling outage. The new 100%' power (3458 MWth/1153 MWe) was first achieved on March 04, 1996. All ,

required Rerate Startup Tests were completed by March 21, j 1996.

There were 12 Special Procedures (SP's) written and J performed in combination with various Surveillance Tests (ST's) described in this report, to successfully achieve the new rating. No adjustments were required to control systems for the following plant systems: EHC - Pressure Regulator, Recirculation, Reactor Core Isolating Cooling (RCIC), or High Pressure Coolant Injection (HPCI). Minor tuning was performed on the '1A' Reactor Feed Pump. All systems performed in a stable manner during the plant startup and during transient testing. The unit is operating very well at rerated conditions.

Limerick 1 Cycle 7 is the first application of a reload quantity of GE-13 fuel. GE-13 is very similar to GE-11 (9x9). GE-13 fuel has part length rods 12 inches longer than.GE-11, 2 Kg more uranium than GE-11 and one more fuel pin spacer grid than GE-11. GE-13 fuel has up to 5% more critical power margin than GE-11 and has 0.8 psi larger bundle delta-P than GE-11 which will require increased recirculation pump speed. GE-13 also required a Tech Spec Safety Limit CPR change, GE13SLCPR = 1.09. 284 bundles of GE-13 have been loaded into Cycle 7.

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Limerick Gcnsrcting Stetion Unit 1 Rerate Startup Test Report Page 3 of 43 PAG:mbc 2.0 PURPOSE This Startup Test Report summarizes the testing performed on Limerick Generating Station (LGS) Unit 1 following the implementation of Power Rerate. The result of Power Rerate is an increase in reactor power equal to 5% of the original rated thermal power. All testing identified within the LGS Updated Final Safety Analysis Report (UFSAR) Chapter 14.2 was addressed and evaluated for applicability to this increased licensed power rating as required by Technical Specification 6.9.1.1. The Rerate Startup Test Program Plan documents these evaluations and describes in detail the

{ tests performed for Power Rerate. Each test performed for Power Rerate is described herein, including the test

[ purpose, description, acceptance criteria and results. This L report is submitted in accordance with the requirements of Technical Specification 6.9.1.1.

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3.0 PROGRAM DESCRIPTION The power rerate startup testing requirements were developed

{ primarily from the review of Chapter 14.2 of the LGS UFSAR, Section 10.3 of the GE Power Rerate Safety Analysis Report for Limerick 1 & 2, and the GE Power Rerate Project Rerate

[ Confirmation Test Program. The results of this testing determined the unit's ability to operate at the rerated power level. The testing was conducted following the sixth

[ refueling outage for Unit 1.

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

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1) Verifying control systems (Feedwater, EHC - Pressure Regulator, and Recirculation) are stable at rerate

[ conditions.

2) Verifying high pressure injection systems (Reactor Core Isolation Cooling, High Pressure Coolant Injection)

[ operate acceptably at rerated pressures.

3) Data collection for comparison to original plant rated

[ conditions (Radiation Surveys, Thermal Performance and Plant Steady State Data).

4) Turbine Control and Stop Valve Testing to determine adequate and safe power levels for future surveillance performances.

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1 Limerick Generating Station Unit 1 Rerate Startup Test Report Page 4 of 43 PAG:mbc Test conditions at which the testing was performed are defined below. All testing with a Test Condition (TC) must be completed prior to proceeding to the subsequent test condition. Reactor core flow can be any flow within the safe operating region of the power / flow map (Figure 1) that will produce the required power level.

Test Condition Rarate Power Level Rorate Mwt 1 <85% <2939 2 85-86% 2939-2974 3 90-91% 3112-3147 4 95-96% 3285-3320 5 97-98% 3354-3388 6 99-100% 3423-3458 All testing within a Test Plateau must be completed and approved by the Startup Test Director, prior to increasing power to the subsequent Test Plateau. Rerate Startup Test Plateaus are defined below.

Test Plateau A (191%) - Includes TC-1,2&3. Reactor Thermal Power cannot exceed 91%.

Test Plateau B (196%) -

Includes TC-4. Reactor Thermal Power cannot exceed 96%.

Test Plateau C (198%) - Includes TC-5. Reactor Thermal Power cannot exceed 98%.

Test Plateau D (1100%) - Includes TC-6. Reactor Thermal Power cannot exceed 100%.

4.0 ACCEPTANCE CRITERIA Level 1 acceptance criteria normally relates to the value of a process variable assigned in the design of the plant, component systems or associated equipment. If a Level 1 criteria is not satisfied, the plant will be put in a suitable hold condition until resolution is obtained. Tests compatible with this hold condition may be continued.

Following resolution, applicab).e tests must be repeated to verify that the requirements of the Level 1 criteria are now satisfied.

Level 2 criterion is associe.ted with expectations relating to the performance of systems. If a Level 2 criterion is not satisfied, operating ar.d testing plans would not necessarily be altered. Investigation of the measurements and the analytical techniques used for the predictions would be started.

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 5 of 43 PAG:mbc Any acceptance criteria failure must be documented on a Test Exception Report (TER).

5.0 RERATE STARTUP TEST PROGRAM

SUMMARY

The test program began when the Mode Switch was placed in startup on February 28, 1996 and ended with all required Rerate Startup Tests complete on March 21, 1996. The unit was synchronized to the grid on March 01, 1996, marking the official end to the Unit 1 sixth refueling outage. The new rerated 100% power (3458 Mwt) was first achieved on March 04, 1996.

In general, the unit operates very well at the rerated conditions. No adjustments were required to control systems for the following: EHC - Pressure Regulator, Recirculation, Reactor Core Isolation Cooling (RCIC), or High Pressure Coolant Injection (HPCI). Minor tuning was performed on the

'1A' Reactor Feed Pump at low power. All systems performed in a stable manner.

Data collected at rerated conditions showed that the 5%

increase in reactor power has little, if any, effect on reactor water chemistry and radiological conditions throughout the plant.

All Rerate Startup Tests were performed satisfactorily during the startup from 1R06 Refueling Outage. Table 3 identifies all of the required Rerate Startup Tests and the Test condition in which each test was performed. There were no Test Exceptions throughout the test program, no Level 1 or Level 2 test failures.

Through startup testing, it has been determined that the Turbine Stop Valve test can be performed at 98% Rerated Power. In addition, it has been determined that Turbine Control Valve testing can be performed at 92% Rerated Power.

These numbers have been revised into the appropriate Surveillance Tests.

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i Limerick Generating Station Unit 1 Rerate Startup Test Report Page 6 of 43 l PAG:mbc l

6.0 TESTING REQUIREMENTS Each of the tests listed in LGS UFSAR Chapter 14.2 were evaluated for applicability to power rerate. Section 6.1 lists the tests (numbered as designated in the UFSAR) not required to be performed for power rerate and the reasons for each determination. Section 6.2 lists the tests (again numbered as designated in the UFSAR) which are required for f power rerate. A description of the specific testing to be performed is included. Table 1 identifies the UFSAR tests and their applicability to power rerate. Testing required to be performed for power rerate will be identified with the same numbering as used in the Initial Startup Program. Table 3 summarizes the testing to be performed and the test conditions for each test performance.

6.1 UFSAR Chapter 14.2 Tests Not Required For Power Rarate 6.1.1 Test 3 - Fuel Loading The purpose of this test is to load fuel safely and efficiently to the full core size. Fuel loading is performed in accordance with FH-605, Core Component Transfer Authorization, during every refueling outage. During the 1R06 outage, fuel will be loaded in accordance with FH-605.

Power rerate has no impact on this evolution; therefore, no additional testing is required.

6.1.2 Test 6 - SRM Performance and Control Rod Sequence This test demonstrated that the operational sources, source range monitoring (SRM) instrumentation, and rod withdrawal sequences provide adequate information to the operator during startup. Technical Specifications and plant procedures ensure proper SRM response during startup. This test does not need to be repeated for rerate.

This test demonstrated the ability to achieve criticality in a safe and efficient manner for each of the two withdrawal sequences and determined the effect of rod motion on reactor power at various operating conditions. The manner in which criticality is achieved is not changed by power rerate. The methods in place do not use 2 sequences. The current withdraw sequence is performed in accordance with Banked Position Withdraw Sequence. The rod patterns for intermediate power levels up to rerated power will f be evaluated using a three dimensional simulator code. Performance of this test is not required.

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 7 of 43 PAG:mbc 6.1.3 Test 9 - Water Level Reference Leg Temperature For LGS the difference in length between the reference legs and the variable legs of water level instrumentation is very small, making correction for the cmall increase in drywell temperatures negligible, therefore this test is not required to be repeated for power rerate, 6.1.4 Test 10 - IRM Performance The purpose of this test was 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 does not need to be repeated for rerate.

6.1.5 Test 13 - Process Computer The purpose of this test was to verify the performance of the process computer under plant operating conditions. The process computer has been fully tested at plant operating conditions.

The functions of the process computar are not changed due to power rerate so no additional testing is required.

6.1.6 Test 16 - Selected Process Temperatures This test established the minimum recirculation pump speed to maintain water temperature in the bottom head of the reactor vessel within 145 F of reactor coolant saturation temperature as i; determined by reactor pressure. This test also

\ provided assurance that the measured bottom head

\ drain line thermocouple was adequate to measure j bottom head coolant temperature during normal operations. Temperature stratification limits are defined within Technical Specifications. This testing is not required for power rerate.

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i 6.1.7 Test 17 - System Expansion

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This test verified that reactor drywell piping and

(\.- ii major equipment were unrestrained with regard to thermal expansion. Analysis was performed for i rerate conditions with results showing that the

[\ piping systems are acceptable for power rerate. No ,

L; further testing is required. I

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Limerick Generating Station Unit 1 Rerate Startup Test Report Page 8 of 43 PAG:mbc ,

t 6.1.8 Test 20 - Steam Production The objective of this test was to operate continuously at rated reactor conditions to demonstrate that the NSSS provided steam at a

. sufficient rate and quality. This was the initial warranty run which is not applicable to power rerate.

6.1.9 Test 23 - Feedwater i

Test 23 had five objectives. The first was to demonstrate reactor water level control. The second was to evaluate and adjust feedwater controls. The third objective demonstrated the capability of automatic flow runback feature to prevent a low water level scram following a single feedwater pump trip. The fourth objective demonstrated adequate response to feedwater heater loss. The final objective demonstrated general reactor response to inlet subcooling changes.

These objectives were demonstrated through the {

performance of three different tests during the  !

initial startup. The tests that will be-performed as part of power rerate are included in Section 6.2.12. Tre tests that are not required for power rerate are described below.

The loss of feedwater heating test demonstrates adeque.te response to loss of feedwater heating.

This event is caused by isolation of the steam extraction line to the feedwater heater. During this transient, the maximum feedwater temperature decrease is required to be 5 100*F, and the resultant MCPR shall be greater than the fuel thermal safety limit. Analysis has been performed for rerate conditions assuming the maximum allowed feedwater temperature decrease of 100*F. The results showed the thermal and mechanical overpowers for this event meet the fuel design

. criteria at rerate conditions. Based on the rerate heat balance, a loss of feedwater heating would not result in a greater than 100*F decrease in final feedwater temperature; therefore, this test is not required to be performed for power rerate.

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. Limerick Generating Station Unit 1 Rerate Startup Test Report Page 9 of 43 PAG:mbc 6.1.9 TEST 23 - Feedwater (Continued)

The feedwater pump' trip test demonstrates the capability of the automatic core flow runback feature to prevent low water level scram following the trip of one feedwater pump. One feedwater pump is tripped and the automatic recirculation runback circuit acts to drop power within the capacity of the remaining feedpumps. This has already been demonstrated at Limerick at MELLA conditions from full power on Unit 1. Data from this evolution was reviewed and it has been determined that

, adequate margin exists for rerate conditions.

G.E. has evaluated one feedwater pump trip and determined that it will not cause a reactor scram with the recirculation runback pump speed set at 42%. Therefore, this test will not be reperformed.

6.1.10 Test 25 - Main Steam Isolation Valves Test 25 had three objectives. The first was to functionally check the MSIVs for proper operation at selected power levels. The second objective determined the reactor transient behavior during and following simultaneous full closure of all MSIVs. The third was to determine the isolation valve closure times. Large transient testing-performed at high power during the Initial Startup demonstrated the adequacy for protection for these large transients. Analysis has shown that for these transients at rerate conditions the change in unit performance is'small, thus testing the unit's response to full closure of the MSIVs at rerate power level is not required. MSIV functional checks will be performed. See Section 6.2.13 for details.

6.1.11 Test 26 - Main Steam Relief Valves This test verified proper operation of the dual purpose relief / safety valves including determination of their capacity and verification of their leaktightness following operation. The ,

valve capacity is not affected by rerate. The I setpoints for these valves are being increased for rerate. The new setpoints will be set and tested.

This test does not need to be performed for power rerate.

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 10 of 43 PAG:mbc 6.1.12 Test 27 - Turbine Trip and Generator Load Rejection Demonstration This test demonstrated the response of the reactor and its control systems to protective trips in the turbine and generator. Large transient testing performed at high power during the Initial Startup demonstrated the adequacy for protection for these large transients. Analysis has shown that for these transients at rerate conditions the change in unit performance is small, thus testing the unit's response to turbine and generator trips at rerate conditions is not required.

6.1.13 Test 28 - Shutdown From Outside the Control Room This test demonstrated 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 aressure and water level controlled from outside the control room. Power rerate does not change the capability of the reactor to be shut down from outside the control room; therefore, a repeat of this test is not required.

6.1.14 Test 29 - Recirculation Flow Control Demonstration This test demonstrated the Recirculation system flow control capability in response to a step change in recirculation flow. Since this same test was just performed during the ARTS /MELLA implementation following 1R05 this test will not be reperformed. During power ascension testing under Mod 6090-1 ARTS /MELLA, recirculation flow step changes were performed in two areas in the new MELLA region while system stability was monitored with positive and negative speed changes (1% to 5%). This test was recently performed on Unit 2 following Power Rerate Implementation with satisfactory results. In both cases, there were no divergent responses, steady state limit cycles, and all decay ratios were less than 0.25.

6.1.15 Test 30 - Recirculation System The first objective of this testing was to determine the transient responses and steady state conditions following recirculation pump trips and to obtain jet pump performance data. The second objective was to calibrate the jet pump flow instrumentation. The recirculation system calibration was performed as Startup Test #35 which will be performed as part of rerate testing (see Section 6.4.2).

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I Limerick Generating Station Unit 1 Rerate Startup Test Report Page 11 of 43 PAG:mbc 6.1.15 Test 30 - Recirculation System (Continued)

Test 30 determined the transient response during recirculation pump trips, flow constdown, and pump restarts. Power rerate does not affect the ability of the recirculation system to respond acceptably to these transients as demonstrated during the i initial Startup Test Program so no further testing l is required.

6.1.16 Test 31 - Loss of Turbine-Generator and Off-Site Power The objectives of this test were to demonstrate proper performance of the reactor and the plant electrical equipment and systems and to verify that safety systems initiate and function properly without manual assistance during the loss of auxiliary power transient. Power rerate will not change the ability of the electrical systems to function properly during a loss of main turbine-generator and offsite power. The ability of HPCI and RCIC to function properly at rerate conditions will be demonstrated (see Sections 6.2.7 and 6.2.8) during the power ascension to rerate conditions; therefore, this test is not required.

6.1.17 Test 33 - Piping Steady-State Vibration Measurements

~This test determined the vibration characteristics of reactor internals and recirculation loops induced by hot two-phase forces. Analysis performed shows that the net impact from power rerate is small and considered negligible. This test is not required to be repeated for power rerate.

6.1.18 Test 34 - Offgas System Performance Verification The purpose of this test during initial startup was to demonstrate that the offgas System operates within Technical Specifications. Power Rerate has been determined to be a minimal impact on this l system and therefore no additional testing outside of normal Technical Specifications is required.

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Limerick Generating Station Unit 1 Rerate Startup Test Report Page 12 of 43 PAG:mbc 6.1.19 Test 36 - Piping Dynamic Transient The objective of the original test was to show that piping vibrations in the Main Steam Inside Containment, Reactor Recirculation and various other systems were acceptable during selected dynamic transients. The small increase in initial power level from power rerate will not significantly change the response of this piping to dynamic transients, thus this test is not required for power rerate.

6.2 UFSAR Chapter 14.2 Tests Recommended For Power Rerate 6.2.1 Test 1 - Chemical and Radiochemical

Purpose:

The primary objective of this test is to maintain control and knowledge about the quality of the reactor coolant chemistry.

Description:

Chemical and radiochemical samples will be taken in accordance with plant procedures at the original 100 % power level and at the rerate 100% power level.

Level 1 Criteria Per ST-5-041-800-1 and ST-5-041-885-1 Level 2 Criteria None Results:

Rorate Chemistry Results PARAMETER ACTUAL DATA ACTUAL DATA ACCEPTANCE (95%) (100%) CRITERIA Primary Rx Coolant 6.26 x 10 4 7.06 x 10 4 10.2 uCi/gm Iodine Primary Rx Coolant 0.084 0.081 11.0 Conductivity Primary Rx Coolant 6.58 6.60 15.6 to 18.6 Ph Primary Rx Coolant 0.26 0.25 1200 Chloride

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 13 of 43 PAG:mbc 6.2.1 Test 1 - Chemical and Radiochemical (Continued)

ST-5-041-800-1 and ST-5-041-855-1 Reactor Coolant Chemistry and Dose Equivalent Iodine -131 respectively were both performed satisfactorily at 95 and 100% rerated power. All acceptance criteria were satisfied.

6.2.2 Test 2 - Radiation Measurements

Purpose:

This test measures radiation levels at selected locations and power conditions to assure the protection of plant personnel and continuous compliance with guideline standards of 10CFR20 during plant operation.

Description:

Radiation levels will be measured at various locations in the plant at rerated power levels of 90% and 100% in accordance with GP-2 App. 6.

Level 1 Criteria Radiation doses of plant origin and occupancy times of personnel in radiation zones shall be controlled consistent with the guidelines of the standards for protection against radiation outlined in 10CFR20 NRC General Design Criteria.

Level 2 Criteria None Results: Radiation Surveys were conducted at rerated power levels of 90 and 100% in accordance with GP-2 Appendix 6, Normal Plant Startup -

Health Physics. Essentially, the dose rates are the same as those experienced at the original power levels. No postings were changed as a result of achieving the rerate 100% power level.

Radiation dose rates remain within the standards for protection against radiation outlined in 10CFR20 NRC General Design Criteria thus meeting the test criteria.

6.2.3 Test 4 - Full Core Shutdown Margin

Purpose:

This test demonstrates that the reactor will be subcritical throughout the fuel cycle with any single control rod fully withdrawn.

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Description:

Shutdown margin demonstrations shall be performed in accordance with ST-3-107-870-1 Shutdown Margin Determination.

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Limerick Generating Station Unit 1 Rerate Startup Test Report Page 14 of 43 PAG:mbc 6.2.3 Test 4 - Full Core Shutdown Margin (Continued)

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

Level 2 Criteria None Results: For Unit 1 Cycle 7, the required shutdown margin must be greater than 0.38% (delta K)/K + R, where R is equal to 0.11% (delta K)/K. Therefore, the calculated shutdown margin for Cycle 7 must be greater than 0.490% (delta K)/K.

As Unit I reached criticality, data was collected to calculate Shutdown Margin in accordance with ST-3-107-870-1, Shutdown Margin Determination.

Cycle 7 shutdown margin was determined to be 1.528% (delta K)/K. This satisfies the Level 1 Acceptance Criteria.

6.2.4 Test 5 - Control Rod Drives

Purpose:

This testing demonstrates that the control rods meet Technical Specification requirements for scram times.

Description:

Scram timing of control rods shall be performed in accordance with ST-3-107-790-1, CRD Scram Timing.

Level 1 Criteria Per ST-3-107-790-1 Level 2 Criteria None Results: Scram Time Testing was performed for 141 control rods during the Operational Hydrostatic Test (Ops Hydro) at rerated pressure. The additional 44 control rods were tested during plant startup at approximately 20% core thermal power. All Level 1 Acceptance Criteria per ST-3-107-790-1, CRD Scram Timing, were satisfied and are shown below.

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Limerick Generating Station Unit 1 Rerate Startup Test Report Page 15 of 43

( PAG:mbc 6.2.4 Test 5 - Control Rod Drives (Continued)

Scram Timing Results Test Position Inserted from Acceptance Acceptance Results Fully Withdrawn Criteria 1 Criteria 2 (seconds) 45 0.43 0.45 0.308 39 0.86 0.92 0.599 25 1.93 2.05 1.300 05 3.49 3.70 2.345 f Acceptanco Criteria 1: Avg. scram insertion time from fully withdrawn position for all control rods.

( Acceptance Criteria 2: Avg. scram insertion time frcm fully withdrawn position for the 3 fastest

( cuntrol rods in each group of 4 control rods in a l 2 by 2 array.

6.2.5 Test 11 - LPRM Calibration f

Purpose:

The purpose of this test is to calibrate the local power range monitors (LPRMs).

Description:

The LPRM channels will be calibrated to make the LPRM readings proportional to the r neutron flux in the narrow-narrow water gap at the l chamber elevation. This calibration will be performed in accordance with ST-3-074-505-1, TIP Calibration of LPRMS.

Level 1 Criteria Per ST-3-074-505-1 Level 2 Criteria f None Results: Using ST-3-074-505-1, TIP Calibration of f LPRMs, all operable LPRMs were successfully calibrated. LPRM Gain Adjustment Factor values for all operable LPRM channels were greater than or equal to 0.90 and less than or equal to 1.10, as required.

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 16 of 43 PAG:mbc 6.2.6 Test 12 - APRM Calibration

Purpose:

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

Description:

Each APRM channel reading will be adjusted to be consistent with the core thermal power as determined from the heat balance. This calibration will be performed in accordance with ST-6-107-887-1, APRM Gain Determination and Adjustment.

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

Level 2 Criteria None Results: APRM Calibrations or Gain Adjustments were performed during each Test Condition (1 through 6) during the Rerate Startup Test Program.

Each performance of ST-6-107-887-1 APRM Gain Determination and Adjustment, was completed satisfactorily. No problems were encountered during these tests.

6.2.7 Test 14 - Reactor Core Isolation Cooling System

Purpose:

This testing will verify proper operation of the Reactor Core Isolation Cooling (RCIC)

System at the rerate operating pressure and provide baseline data for future surveillance testing. Data obtained during the rated pressure quick start test will be analyzed to verify the margin to trip on RCIC Turbine Speed following a quick start to satisfy SIL 377 commitment.

Description:

At 150 psig, as part of the normal plant startup, ST-6-049-320-1, RCIC Operability Verification (or the appropriate Special Procedure), will be performed to demonstrate adequate control of the turbine and rated flow capability.

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l Limerick Generating Station Unit 1 Rerate Startup Test Report Page 17 of 43 l PAG:mbc

, 6.2.7 Test 14 - Reactor Core Isolation Cooling System l (Continued)

Using the current controller settings, a condensate storage tank (CST) injection is performed at > 920 psig to demonstrate acceptable operation at the lower end of the operating pressure range for power rerate and to provide a l

benchmark to which future surveillance tests are compared. This demonstration will be performed using ST-6-049-230-1, RCIC Pump, Valve and Flow Test' (or the appropriate Special Procedure). A stability check of the RCIC system will be performed in accordance with station procedures or the appropriate Special Procedure.

I At rerate operating pressure, a cold quick start is performed in accordance with S49.1.D, RCIC System Full Flow Functional Test (or the

'g appropriate Special Procedure). Following the quick start, system stability shall be lg demonstrated by introducing small step

! disturbances in flow demand in accordance with I station procedures or the appropriate Special l Procedure. As part of the analysis of the RCIC quick start at rated conditions, the margin to trip on RCIC turbine speed will be measured to determine if the recommended modification of SIL 377 is needed.

Level 1 Criteria

1. The system shall deliver rated flow (600 gpm)

I in less than or equal to 55 seconds automatic initiation at any reactor between 150 psig and rated pressure from the pressure at rerate conditions.

2. The RCIC turbine shall not trip or isolate during auto or manual starts.

NOTE: If any Level 1 criteria are not met, the reactor will only be allowed to operate up to a restricted power level defined by Figure 2 until the Level 1 criteria are met. Consult Technical Specifications for other actions to be taken.

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Unit 1 Rerate Startup Test Report Page 18 of 43 PAG:mbc 6.2.7 Test 14 - Reactor Core Isolation Cooling System (Continued)

Level 2 Criteria

1. To provide an overspeed and isolation trip avoidance margin, the transient start first and subsequent speed peaks shall not be more than 5% faster than rated RCIC turbine speed.

2. The speed and flow control loops shall be adjusted so that the decay ratio of any RCIC system related variable is not greater than 0.25.

Results: At 150 psig, SP-146, RCIC Operability Verification for Power Rerate, was performed satisfactorily. The purpose of this test was to verify RCIC Operability at 150 psig and verify time to rated flow falls within 30 seconds. Tech Spec minimum for rated flow is 600 gpm and actual was 700 gpm. Time to rated flow was 41.5 seconds thus satisfying all criteria.

With reactor pressure at approximately 960 psig, the RCIC Pump, Valve and Flow Test, ST-6-049-230-1, was performed satisfactorily. The RCIC turbine did not trip, greater than 600 gpm was achieved with discharge pressure greater than 70 psig above reactor pressure in less than 55 seconds, thus satisfying all Level 1 acceptance criteria. All speed peaks were less than 4803.75 rpm satisfying the Level 2 criterion.

Section 7.3 of SP-146, Unic 2 RCIC Operahi:.ity Verification for Power Rerate, was performed satisfactorily at 100% Rerated Power Level. A cold quick start was performed and stability was checked. RCIC pump flow was 600 gpm at a pressure of 1280 psig and time to rated flow was 19 seconds with an initial speed spike of 2100 rpm. No tuning was needed and the system ran smoothly.

Decay ratios were zero. All Level 1 and 2 acceptance criteria was satisfied.

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 19 of 43 PAG:mbc 6.2.8 Test 15 - High Pressure Coolant Injection System

Purpose:

This test will verify proper operation of the High Pressure Coolant Injection (HPCI) System at the rerate operating pressure and provide baseline data for future surveillance testing.

Description:

At 200 psig, as part of the normal ,

plant startup, ST-1-055-800-1, HPCI Response Time (or the appropriate Special Procedure), will be performed to demonstrate adequate control of the turbine and rated flow capability.

Using the current controller settings, a condensate storage tank (CST) injection is performed at 920 psig to demonstrate acceptable operation at the lower end of the operating pressure range for power rerate and to provide a benchmark to which future surveillance tests are compared. This demonstration will be performed using ST-6-055-230-1, HPCI Pump, Valve and Flow (or the appropriate Special Procedure). A stability check of the HPCI system will be performed in accordance with station procedures or the appropriate Special Procedure.

At rerate operating pressure, a cold quick start is performed in accordance with S55.1.D, Full Flow Functional Operating Procedure (or the appropriate Special Procedure). Following the quick start, system stability shall be demonstrated by introducing small step disturbances in flow demand in accordance'with station procedures or the appropriate Special Procedure.

Level 1 Criteria

1. The system shall deliver rated flow (5600 gpm) in less than or equal to 60 seconds from the automatic initiation at any reactor pressure between 200 psig and rated pressure at rerate conditions.

2. The HPCI turbine shall not trip or isolate during auto or manual starts.

I i

LimDrick Ganerating~ Station-Unit 1 Rerate Startup Test Report Page 20 of 43 PAG:mbc 6.2.8 Test 15 - HPCI System (Continued)

Level 2 Criteria

1. To provide an overspeed and isolation trip avoidance margin, the transient start first speed peak shall not be within 15% (of rated turbine speed) of the overspeed trip, and subsequent speed peaks shall not be more than 5% faster than rated HPCI turbine speed.

2. The speed and flow control loops shall be adjusted so that the decay ratio of any HPCI system related variable is not greater than 0 . 2 5 .,

Results: At 200 psig, SP-145, HPCI Operability Verification for Power Rerate, was performed satisfactorily. The purpose of this test was to verify HPCI operability at 200 psig and verify time to rated flow falls within 60 seconds. Tech Spec minimum flow is 5600 gpm and actual was 5600 gpm at a discharge pressure of 410 psig. Turbine speed was 3800 rpm and the turbine did not trip.

Time to rated flow was 40 seconds thus satisfying all Level 1 and Level 2 criterion.

At 960 psig,4ST-6-055-230-1, HPCI' Pump, Valve and Flow, was completed satisfactorily. The following acceptance criteria were met:

Rated Flow 5600 Actual 5700 gpm Rated Pressure 1100 psig Actual 1125 psig Response Time 60 sec Actual 25.9 sec No speed requirements were exceeded. The speed and flow control loops did not need any adjustment and decay ratio was less than 0.25 thus satisfying all test criterion.

SP-145, HPCI Operability Verification for Power Rerate, was performed satisfactorily at 100%

Rerated Power. A cold quick start was performed in conjunction with a stability (tuning) check.

No turbine trip or isolations were received and the following test acceptance criteria was met:

Rated Flow 5600 Actual 5600 Rated Pressure 1100 Actual 1300 Decay Ratio 1 25 Actual 1 25

, Response Time 60 Actual 20.9 sec

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 21 of 43 PAG:mbc 6.2.8 Test 15 - HPCI System (Continued)

The transient start peak speed did not exceed the l limit of 4609 rpm and subsequent peaks were less than maximum allowable 4400 rpm. All Level 1 and 2 acceptance criteria were met.

6.2.9 Test 18 - TIP Uncertainty

Purpose:

This test confirms the reproducibility of l the traversing incore probe system (TIPS) readings, determines the core power distribution in three dimensions, and determines core symmetry.

Description:

This test is performed in accordance with RT-3-074-850-0, Core Power Symmetry and TIP Reproducibility.

Level 1 Criteria None m Level 2 Criteria L Per RT-3-074-850-0 F

Results: RT-3-074-850-0, Core Power Symmetry and ,

TIP Reproducibility, was performed satisfactorily

( at full power. Reactor Power distribution data was collected by repeatedly traversing the core axially with gamma tips. This data was collected and forwarded to the Fuel and Services Division

[

for analysis. The results are below:

Random Noise Geometric Total Tip Component (%) Component (%) Uncertainty (%)

{

0.71% 0.90% 1.14%

Thus the requirement of total tip uncertainty to

( be 17.1% was satisfied.

6.2.10 Test 19 - Core Performance

[

Purpose:

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

Description:

As power is increased along a constant rod pattern line, core thermal power will be measured near 90% rerated power and at each 3%

increment up to 100% rerate power, using the current plant methods of monitoring reactor power.

Limerick Generating St9 tion Unit 1 Rerate Startup Test Report Page 22 of 43 PAG:mbc 6.2.10 Test 19 - Core Performance (Continued)

Demonstration of fuel thermal margin will be performed prior to and during power ascension at each 3% increment up to the rerated power level.

Fuel thermal margin will be projected to the next test point to show expected acceptable margin, and will be satisfactorily confirmed by the measurements taken at each test point before advancing to the next increment.

i This demonstration and on-going monitoring of core and fuel conditions will be performed in accordance with ST-6-107- 885-1, Thermal Limits (or the appropriate Special Procedure).

Level 1 Criteria ,

The following thermal limits are s 1.000:

1. CMFLPD (Core Maximum Fraction of Limiting Power Density) l I

2. CMFCP (Core Maximum Fraction of Critical Power)

3. CMAPR (Core Maximum Average Planar Ratio)

Level 2 Criteria 1

None l

Results: While thermal limits are continuously monitored during power ascension ST-6-107-885-1, Thermal Limits, was performed at each test l condition satisfactorily thus meeting all acceptance criteria.

Rerate Power Level 95% 98% 100%

Thermal Limit 89%

MFLCPR .856 .860 j .863 .884 MFLPD .839 .850 .827 .873 MAPRAT .864 .860 .820 .866

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 23 of 43 PAG:mbc 6.2.11 Test 22 - Pressure Regulator

Purpose:

This test has three objectives.

% 1. To confirm the adequacy of the settings for 1 the pressure control loop by analysis of the transients induced in the reactor pressure control system by means of the pressure regulators.

2. To demonstrate the backup capability of the pressur e regulators via simulated failure of the cot. trolling pressure regulator.

3. To demonstrate that other affected parameters are within acceptable limits during pressure induced transient maneuvers.

Description:

During TC-1 and TC-2, the following step inputs will be made to the pressure regulator:

1. -3 psi

2. +3 psi

3. -5 psi

4. +5 psi

5. -10 psi

6. +10 psi When this testing is complete for one pressure regulator, transfer is made to the other pressure J regulator, and the steps shall be repeated.

( Transfer back to the original pressure regulator is accomplished through simulated failure of the controlling pressure regulator. Transfer between pressure regulators by normal transfer and by simulated failure demonstrate that these events are survivable and well-behaved.

Average main steam line flow versus pressure regulator output is taken in increments of 2%

power during the power ascension to 100% rerate power. The variation in the slope of the curve plotted on linear graph paper must show that the incremental regulation is within the criteria. If the requireraents are not met, the control valve function generator break points will have to be adjusted.

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 24 of 43 PAG:mbc 6.2.11 Test 22 - Pressure Regulator (Continued)

Level 1 Criteria The transient response of any pressure control system related variable to any test input must not diverge.

Level 2 Criteria

1. Pressure control system related variables mar contain oscillatory modes of response. In these cases, the decay ratio for each controlled mode of response must be less than f or equal to 0.25. (This criterion does net apply to tests involving simulated failure of one regulator with the backup regulator f taking over.) {

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

3. Pressure control system deadband, delay, etc., shall be small enough that steady state limit cycles (if anyj shall produce steam flow variations no larger than +0.5% of rated steam flow.

4. The peak neutron flux and/or peak vessel pressure shall remain below the scram settings by 7.5% and 10 psi respectively for all pressure regulator transients.

5. The variation in incremental regulation (ratio of the maximum to the minimum value of

" incremental change in pressure the quantity, control / incremental change in steam signal flow", for each flow range) shall meet the following:

[  % of Steam Flow Obtained l With Valves Wide Open Variation 0 to 8S% $ 4:1 85% to 97% i 2,1 85% to 99% 1 5:1

6. Turbine control valves 1, 2, and 3 must be full open when the fourth valve is about 10%

open and has full control of reactor e pressure.

Limerick Gnnerating Station Unit 1 Rerate Stcrtup Test Report Page 25 of 43 _

PAG:mbc 6.2.11 Test 22 - Pressure Regulator (Continued $

Results: Pressure regulator stability testing was performed at rerate power levels of 30% and 95%.

The data obtained during each test condition is -

[

i summarized below. The system response to all size step changes at each power level was excellent.

- There were no signs of divergence or oscillations.

Decay ratios were zero for all step changes.

y Pressure response time and margins to scram setpoints were satisfactory in all caseo. No limit cycles were observed. All Level 1 and Level 2 acceptance criteria were satisfied, f "A" PRESSURE REGULATOR STEP CHANGE DATA Peak Pressurc Peak Steady Power Step Step Pressure Response Power State Level (+/-) Size (psig) Time (sec) ,

(%) Cycles 3 2.5 968.5 t 4.2 31.1 0 5 4 969.3 4 32 0 r 30% '

10 8.75 972 4.2 34.1 0 3

23 1028.3 4.2 95.83 0 95% 5 5.0 1028.6 3.7 96.94 0 10 10 1030 3.6 99.17 0 "B" PRESSURE REGULATOR STEP CHANGE DATA _

Peak Pressure Peak Steady Power Step Step Pressure Response Powin S tM.e f _ Level (+/-) Size (psig) Time (sec) (%'; _ Cyr)es

" 3 3.75 969.5 3.8 31.5 0 5 5.5 970.5 4 32.6 0 -

30% __

10 10 973.5 3.9 34.9 0

[

[ ,

3 3.3 1028.3 3.6 95.E3 0 .,

95% 5 6.1 1028.1 2.8 96.11 0 10 12.2 1030.0 3.1 99.17 ,

O l r

r

I I

l

~

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 26 of 43 PAG:mbc g Test 22 - Pressure Regulator (Continued)

N 6.2.11 l l

{ Pressure Regulator failovers were performed at i i

l rerate power levels of 30% and 95%. The data obtained is summarized below. In all cases, the l backup pressure regulator took control when the

- controlling regulator was failed. All acceptance criteria were satisfied.

Pressure Regulator A PRESSURE REGULATOR FAILOVER DATA  ;

l Peak Pressure Peak Steady lI i Power Step Pressure Response Power State Level Size (psig) Time (sec) (%) Cycles 30% 13.8 985 2.2 42.9 0 h ,

( 95% 11.7 1043.9 4.4 100.3 0  !

E Pressure Regulator B l i

PRESSURE REGULATOR FAILOVER DATA '

l Fr ;k Pressure Peak Steady

[ Response Power State Power Step Pressure Level Size (psig) Time (sec) (%) Cycles 30% 11.5 981.8 2.3 39.25 0 1

, 95% 11.7 1042.8 4.1 100 0 Pressure Regulator Incremental Regulation  !

Determination, SP-142, was performed in 2% power I increments from main generator synchronization to full power. This data was used to calculate the pressure regulator incremented regulation. All test criteria were satisfied and are summarized below. Turbine control valves 1, 2, and 3 were full open when the fourth valve was approximately

$ 10% open and had full control of reactor pressure.

E 7"" O Steam Flow Incremental Regulation Variation Level 2 I

han98 Maximum Minimum 0% to 85% 1.33 0.35 3.83 14:1 I 85% to 97% 1.14 0 . f.1 1.86 12:1 85% to 99% 1.14 0.61 1.86 15:1 I

I

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 27 of 43 PAG:mbc 6.2.12 Test 23 - Feedwater System

Purpose:

To verify that the feedwater system has been adjusted to provide acceptable reactor water level control at rerated conditions.

Description:

Reactor water level setpoint changes of approximately 3 to 6 inches will be used to evaluate and acceptably adjust, if necessary, the feedwater control system settings for power and feedwater pump modes tested. The level setpoint changes will be performed in accordance with the appropriate Special Procedure.

Level setpoint changes shall be performed at four (4) power levels: 30%, 60%, 95% and 98%.

Total feedwater flow and Master level controller output data is taken in 3% to 5% increments to 100% rerate power. The variation in the slope of the curve plotted on linear graph paper (feedwater controller output versus total feedwater flow) must show that the incremental regulation is within the criteria.

Level 1 Criteria The tre.nsient response of any level control system related variable to any test input shall not diverge.

Level 2 Criteria

1. Level control system related variables may contain oscillatory modes of response. In these cases, the decay ratio for each controlled mode of response shall be less than or equal to 0.25.

2. At steady state generation for the 3/1 element systems, the input scaling to the mismatch gain shall be adjusted such that level error due to biased mismatch gain output shall be within 1 inch.

3. The variation in incremental regulation (feedwater flow demand changa divided by actual feedwater flow change for small disturbances) does not exceed a factor of 2 tc 1 between feedwater flow demand and feedwater flow.

Limerick Gnnerating Station Unit 1 Rerate Startup Test Report Page 28 of 43 PAG:mbc 6.2.12 Test 23 - Feedwater System (Continued)

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

Results: Feedwater Stability Testing was performed at rerated power levels of 30, 60, 95, and 98%.

Two inch and five inch 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.

Cystem response was not oscillatory and showed no signs of divergence. Minor tuning was performed on the '1A' Reactor Feed Pump at 30% core thermal power. No other tuning or adjustments were necessary. All acceptance criteria related to system stability was satisfied.

Speed regulation tests were performed during'the 1R06 outage on all three reactor feed pumps. The results are tabulated below and the turbine speed regulation variation between the three feed pumps matched within i6% of rated speed.

M-006-003 M-006-003 M-006-003 RFPT A RFPT B RFPT C RFPT

% 6.20 6.22 6.22 RPM /In. 134.67 134.69 134.67 The level error between single and three element level control was verified following the stability testing at 30, 60, 95 and 98% power levels. The level never changed by more than 1 inch on each transfer. All test acceptance criteria was satisfactory.

Feedwater controller output and feedwater flow data was collected approximately every 3-5% power during power ascension in accordance with SP-144, Feedwater Incremental Regulation Determination.

Data was taken and plotted for both 2 pump and 3 pump configurations and the variation in incremental regulation was 12:1 for both conditions.

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 29 of 43 PAG:mbc 6.2.13 Test 24 - Main Turbine Valves-Surveillance Test Purpose This test determines the highest power level ct which surveillance testing can be perforzed on the. Turbine stop and Control valves without causing a reactor scram.

Description:

Individual main turbine valves are f tested routinely during plant operation as required for turbine surveillance testing. Turbine stop and Control Valves shall be individually stroked at various power levels in accordance with the appropriate Special procedure to determine the highest power at which the normal surveillance testing can be performed.

Level 1 Criteria None Level 2 Criteria

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

2. Peak vessel pressure must remain at least 10 psi below the high pressure scram setting.

j 3. Peak steam flow in each line must remain 10%

below the high flow isolation trip setting.

Resulta In order to have data from which to extrapolate, Turbine Stop Valve testing was initie.11y performed at 86% power. APRM peake, l

Mein steam line flow peaks, and Reactor High l- Pressure peaks were collected, graphed, and extrapolated up at power levels of 86, 90, 95 and 93%. A test was started at 100%, however, was aborted after stroking one valve due to_a bypass valve opening. Under these conditions, all test criteria were satisfied and future performances will be performed by adjusting power to 98% core thermal power. Data is summarized below.

)

)

[ l Limerick Gsnerating Station Unit 1 Rerate Startup Test Report Page 30 of 43

[ PAG:mbc L

6.2.13 Test 24 - Main Turbine Valves Surveillance Test (Continued)

Reactor High Pressure Peak Test Power Levels (%)

86 90 95 98 Reactor Pressure Peak (psig)

SV Test SV1 1025.4 1032.5 1041.1 1045.3 Sv2 1023.8 1031.4 1039.2 1044.2 Sv3 1025.4 1032.5 1040 1045.2 Sv4 1024.2 1031.1 1038.6 1043.6 MSL Flow Peaks MSL FLOW Peek (MLb/hr)

SV TEST Test Pwr MSL A MSL 8 MSL C MSL D SV1 3.06 3.35 3.125 3.5 Sv2 3.46 3.23 3.12 3.58 86 SV3 3.06 3.31 3.625 3.48 SV4 3.00 3.04 3.44 3.31 f

SV1 3.76 3.57 3.31 3.68 SV2 3.67 3.38 3.79 3.28

[ Sv3 90 3.27 3.53 3.82 3.71 SV4 3.69 3.19 3.65 3.51 SV1 4.00 3.83 3.50 3.83 SV2 3.92 3.71 3.99 3.47 r 95 SV3 3.50 3.78 4.03 3.90

[

SV4 3.93 3.42 3.88 3.74 SV1 4.15 3.97 3.75 4.00 SV2 4.06 3.88 4.13 3.60 98 SV3 3.72 3.88 4.17 4.06 Sv4 4.1 3.53 4.0 3.88 t

LimDrick Gsnerating Station Unit 1 Rerate Startup Test Report Page 31 of 43 PAG:mbc 6.2.13 Test 24 - Main Turbine Valves surveillance Test (Continued)

Flux Peaks APRM Peak (%)

8 D E F SV TEST Test A C Pwr SV1 88.3 89.1 88.75 87.6 87.7 87.8 Sv2 87.7 87.8 87.5 87.6 87.4 87.3 86 Sv3 89.0 89.3 88.75 88.3 88.2 88.3 SV4 87.7 88.0 87.9 87.4 87.1 87.0 SV1 90.34 92.76 92.93 91.9 93.10 92.24 Sv2 89.83- 92.41 92.07 92.8 92.59 91.72 90 SV3 90.52 92.93 92.93 91.9 93.28 92.41 SV4 89.48 92.07 91.90 92.8 92.41 91.72 SV1 98.97 97.93 98.97 98.28 98.62 97.07

' Sv2 97.76 97.07 97.93 97.07 97.67  %.03

~

95 SV3 98.1 97.59 98.62 97.76 98.1  %.72 SV4 97.41  %.38 97.41 96.55 97.24 95.52 SV1 100.26 99.74 100.% 100. % 100.61 99.56 _

SV2 100.26 99.91 100.79 100.26 100.44 99.39 _

98 SV3 100.79 100.26 101.14 100.% 100.% 100.26 _

Sv4 100.09 99.39 100.26 100.26 100.09 99. 2'>.

1

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 32 of 43 PAG:mbc 6.2.13 Test 24 - Main Turbine Valves Surveillance Test (Continued)

In order to have data from which to extrapolate, Turbine control Valve testing was initially performed at 86% power. APRM peaks, Main Steam Line flow peaks, and Reactor High Pressure peaks were collected, graphed and extrapolated up at. l power levels of 86, 90, and 92% power. The 95%

data was not acceptable from the standpoint of bypass valves opening. Therefore, future performances of the Turbine Control Valve test will be performed at 92% Rerate Power where all test criteria were found acceptable. Data is summarized below.

Reactor High Pressure Peak Test Power Levels (%)

86 88 90 92 95 CV Test Reactor Pressure Peak (psig)

CV1 1022.5 1026.7 1029.7 1033.3 1036.9 CV2 1022.5 1026.7 1030.0 1033.9 1036.7 CV3 1022.5 1026.7 1030.0 1033.3 1037.2 CV4 N/A 1019.2 1024.7 1033.1 1038.1

l Limerick Generating Station l Unit 1 Rerate Startup Test Report Page 33 of 43 PAG:mbc

, 6.2.13 Test 24 - Main Turbine valves Surveillance Test (Continued)

MSL Flow Peeks MSL FLOW Peak (Mlb/hr)

CV TEST Test Pwr MSL A ' 4L 8

. MSL C MSL D Cv1 3.21 6 12 3.23 3.17 CV2 3.23 3.12 3.21 'I.15 86 CV3 3.21 3.12 3.23 3.11 CV4 N/A N/A N/A N/A CV1 3.38 3.27 3.40 3.33 Cv2 3.40 3.29 3.38 3.33 88 CV3 3.40 3.29 3.38 3.35 CV4 3.21 3.12 3.21 3.15 CV1 3.49 3.35 3.46 3.42 CV2 3.47 3.36 3.46 3.39 90 CV3 3.50 3.39 3.47 3.36 CV4 3.36 3.28 3.36 3.28 CV1 3.56 3.39 3.57 3.42 CV2 3.56 3.39 3.56 3.47 92 CV3 3.57 3.46 3.57 3.49 CV4 3.56 3.38 3.54 3.49 CV1 3.65 3.54 3.67 3.57 CV2 3.68 3.54 3.65 3.58 95 CV3 3.67 3.54 3.65 3.60 CV4 3.65 3.54 3.63 3.56

Limarick Genornting Stction Unit 1 Rerate Startup Test Report Page 34 of 43 PAG:mbc 6.2.13 Test 24 - Main Turbine Valves Survaillance Test (Continued)

Flux Peaks APRM Peak (%)

D E F Test A 8 C CV TEST Pwr CV1 88.1 88.5 88.30 87.9 87.6 87.6 CV2 88.2 88.8 87.90 88.1 87.6 87.3 86 CV3 88.2 88.6 87.90 87.9 87.6 87.6 _

CV4 N/A N/A N/A N/A N/A Ng CV1 92.5 93.3 92.60 92.2 92.1 92.2 CV2 91.1 92.10 91.10 90.9 90.5 90.5 I CV3 88 90.5 91.20 90.6 90.2 90.0 90.0 C74 88.6 88.80 88.3 88.6 87.8 87.9 C' /1 91.03 93.45 93.45 92.8 93.79 93.28 C-./2 90.34 92.76 92.76 91.9 93.10 92.41 Cv3 89.31 91.90 92.07 91.7 92.41 91.55 CV4 88.45 90.86 90.69 91.7 91.38 90.52 CV1 93.28 95.34 95.69  %.4 96.38 95.52 i CV2 CV3 92 92.31 93.10 95.27 94.14 95.5?

94. 31

~

95.8

%.1 95.86 94.83 95.00 94.14 CV4 91.9 94.14 4.48 95 95.00 93.97 CV1 98.28 97.76 98 45 97.93 98.28  %.72 Cv2 98.1 97.41 98 8.3 97.76 98.1  %.72 I CV3 95 98.62 98.10 99.14 98.2f 98.26 97.07 CV4 98.62 97.93 98.97 98.1 98.62 97.07 6.2.14 Test 35 - Recirculation and Jet Purnp l Instrumentation Calibration

Purpose:

The purpose of this test is to perform a L complete calibration cf the installed recirculation system flow instrumentation including specific signals to the plant process

[ computer.

E W

b Limerick Generating Station Unit 1 Rerate Startup Test Report Page 35 of 43 PAG:mbc 6.2.14 Test 35 - Recirculation and Jet Pnap Instrumentation Calibration (Continued)

Description:

At operating conditions which allow the recirculation system to operate at the speeds required for rated flow at 100% rerate power, the jet pump flow instrumentation will be adjusted to provide correct flow indication based on the jet pump flow. The total core flow signal to the process computer will be calibrated to accurately read the total core flow. This recalibration of the recirculation system shall be performed in accordance with ST-2-043-500-1, Recirculation System Flow Calibration.

Level 1 Criteria Per ST-2-043-500-1 Level 2 Criteria None Results: Core flow calibration was performed per ST-2-043-500-1, Recirculation System Flow

, Calibration. Data was collected and core flow calculations were performed and the M-ratio converged to 11.0%. Jet Pump Flow Summer Amplifier gain adjustment factors were calculated and were between 0.99 and 1.01 meeting the acceptance criteria without needing adjustments.

In addition, the APRM/RBM flow unit gain adjustment factors were calculated and also did not need adjustment. All acceptance criteria were met.

6.2.15 Test 32 - Essential HVAC System Operation and Containment Hot Penetration Temperature verification

Purpose:

The purpose of this test as written for the Initial Startup Test program was to verify the ability of the Drywell Atmosphere Cooling System to maintain design conditions in the drywell during operating conditions.

Description:

Drp-ell temperature is monitored to ensure design limits are not exceeded. There are no changes for rerate which will affect the air flow distribution inside the drywell. The calculated increase in drywell temperature resulting from rerate is 2*F. Drywell temperatures will be monitored in accordance with ST-6-107-590-1.

I Limerick Generating Station Unit 1 Rerate Startup Test Report Page 36 of 43

{ PAG:mbc 6.2.16 Test 32 - Essential HVAC System Operation and Containment Hot Penetration Temperature Verification (Continued)

Level 1 Criteria Drywell temperature shall not exceed 135*F per Tech Spec 3.6.1.7.

Level 2 Criteria None Results: Drywell average air temperature is monitored per ST-6-107-590-1, Daily Log - Opcons

[- 1, 2, 3. Drywell average air temperature remained 1130 F thus meeting the acceptance criteria of 1135* F.

6.2.16 Survaillance Testing Surveillance testing shall be performed on all Tech Spec instrumentation requiring recalibration due to power rerate changes (i.e. setpoint change, range change, etc.). A Special Procedure will contain signoffs for all the required surveillance tests. Instrumentation required for monitoring during startup testing is addressed in Sections 7.2 and 7.3.

Resultss;All Surveillance Testing required for Tech Spec related' instrumentation affected by power rerate changes were completed satisfactorily. A Special Procedure, SP-138, f Surveillance Testing for Tech Spec Instrumentation, was Written and performed to capture all of the applicable Surveillance Tests with the exception of the RBM Surveillance Tests

{ which were performed prior to exceeding 30% power.

6.2.17 steady State Data Collection Steady state data of important plant parameters, as determined by the Performance and Reliability f Group and Plant Engineering, shall be obtained following power rerate implementation at each incremental power increase between approximately 85.7% (90% original power) and 100% rerate power.

The data taken at power levels less than 100%

shall be extrapolated to predict conditions at r 100% rerate power. This data collection shall be performed as a Special Procedure.

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 37 of 43 PAG:mbc 6.2.18 Steady State Data Collection (Continued)

Results: Data was collected for 156 plant parameters at Test Conditions 2 through 6. For the most part the data tracked very well. There were a few points that were generating bad data and after investigation had Equipment Trouble Tags (ETTs) filled out for them. These points were not f critical and were documented with discrepancy forms in the governing data collection procedure SP-137, Steady State Data Collection.

Extrapolations were made for various instruments recording Turbine first stage pressure, Total heactor Steam flow, Reactor Feedwater temperatures and Turbine Control valve positions. During the sttartup EHC pressure set was set at 960 psig, this setting achieved only 1038 psig in the Reactor Vessel during the initial rise to 100% reactor f power. Subsequently, pressure set was adjusted to approximately 967 psig in order to achieve the 100% rated pressure of 1045 psig.

, 6.2.18 Thermal Performance Steady state data on thermal performance parameters, as determined by the Performance and Reliability Group and Plant Engineering, will be obtained when the unit reaches original 100%

power, 3293 MWt. The same data shall be collected f at steady state conditions at the rerate power level of 100%, 3458 MWt.

Results: The Thermal Performance data was collected per SP-135, Thermal Performance Data f

Collection and Baseline for Rerated Conditions.

l This test was designed to baseline the Thermal Performance of Unit 1 at rerated conditions and to determine the gross / net generator electrical f output change which occurs as a recult of implementing power rerate. There is no acceptance criteria for this test. In an attemr; to obtain

( true delta data for power rerate and'not confuse i changes due to outage work (i.e., condenser cleaning) the test was run at 3293 Mwth 1005 psig and again at 3458 Mwth 1045 psig during the power ascension testing.

1 Limerick Generating Station Unit 1 Rerate Startup Test Report Page 38 of 43 PAG:mbc This concludes the LGS Unit 1 Rerate Startup Test Report.

Prepared By: M Rerate Startup Test Director Reviewed By: -

Manager - Reactor Engineering Approved By:

' Director of' Site Encfineering I

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Limerick Generating Station 5 Unit 1 Rerate Startup Test Report

/ Page 39 of 43 PAG:mbc TABLE 1 - UFSAR Chapter 14.2 Tests UFSAR STP # Test Required for Rerate 1 Chemical and Radiochemical Yes 2 Radiation Measurements Yes 3 Fuel Loading No 4 Shutdown Margin Yes 5 Control Rod Drives Yes 6 SRM Performance No 9 Water Level Ref Temp No 10 IRM Performance No 11 LPRM Calibration Yes 12 APRM Calibration Yes 13 _

Process Computer (PMS) No 14 Reactor Core Isolation Cooling Yes 15 High Pressure Coolant Injection Yes 16 Selected Process Temps. No 17 System Expansion No 18 TIP Uncertainty Yes 19 Core Performance Yes 20 Steam Production No 22 Pressure Regulator Yes 23 Feedwater System Yes 24 Main Turbine Vlv Sury. Test Yes 25 Main Steam Isolation Valves No 26 Main Steam Relief Valves No 27 Turbine Trip and Generator Load No Re]ection Demo 28 Shutdown From Outside the Main No Control Room 29 Recirc Flow Control Demo No 30 Recirculation System No 31 L ss of Turbine-Generator and No Off-Site Power 32 Essential HVAC Sys Oper and Hot No Temp Verification 33 Piping Steady-State Vibration No Measurements 34 Offgas Sys Performance No Verification 35 Recirculation Flow Cal Yes 36 Piping Dynamic Transient No 70 RWCU Perf. Verification No 71 RHR Perf. Verification No

Limerick Generating Station Unit 1 Rerate Startup Test Report i

Page 40 of 43 PAG:mbc Test Conditions l TEST CONDITIOR RERATE POWER LEVEL i 1 2

<85%

85%-86% (Note 2) 3 90%-91%

4 95%-96% (Note 3)

I 5 97%-98%

6 99%-100% (Note 4) l NOTES: 1) 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.

2) Original 90% power is equal to 85.7% rerate power.

3) Original 100% power is equal to 95.23% rerate power.

4) 100% rerate power is equal to 3458 MWt.

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Limerick Generating Station Unit 1 Rerate Startup Test Report Page 41 of 43 PAG:mbc TABLE 3 -

Tests to be Performed for Power Rerate Test Condition STP # Test Description 1 2 3 4 5 6 Chemical & Radiochemical X X 1

2 Radiation Measurements X X 4 Shutdown Margin X 5 CRD Scram Timing X 11 LPRM Calibration X 12 APRM Calibration X X X X X X 14 RCIC (150#) X 14 RCIC (2 920#) X 14 RCIC Stability (Rerated X Pressure) 14 RCIC Cold Quick Start X 15 HPCI (200#) X 15 HPCI (2 920#) X 15 HPCI Stability (Rerated X Pressure) 15 HPCI Cold Quick Start X 18 TIP Uncertainty X 19 Core Performance X X X X 22 Pressure Regulator 3 X X 23 Feedwater Level Control' X X X X 24 Turbine Stop Valve ST X X X X X 24 Turbine Control Valve ST' X X X 35 Recirc. System Flow X Calibration N/A Thermal Performance Test X X N/A I&C Surveillance Tests 2 X N/A Steady State Data X X X X X Collection 1- Levet setpoint changes wiLL be performed four times, once each at approximate rerate power levels of 30%, 60%, 95%, and 98%.

2- These are to be performed prior to the plant condition for which the instrument is required to be operable.

3- Pressure Regulator stability checks wiLL be performed at approximate rerate power Levels of 30% and 95%.

4- Turbine Control Valve ST wiLL be performed at power Levels of 86, 88, 90, 92 and 95%.

Limerick Generating Station Unit 1 Rerate Startup Test Report Page 42 of 43 PAG:mbc FIGURE 1 ReratePower/FlowMap 130 -130 120 / p 120 no-100 1100P/81P

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( Limerick Generating Station Unit 1 Rerate Startup Test Report Page 43 of 43 PAG:mbc

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