Deletion of Turbine Trip Test at Test Condition 3 from Power Ascension Test Program During Conduct of Test Number 25-Turbine Trip & Generator Load Rejection, Safety EvaluationML20137F393 |
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Hope Creek |
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Issue date: |
08/20/1985 |
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Public Service Enterprise Group |
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Shared Package |
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ML20137F347 |
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References |
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PSE-SE-Z-001, PSE-SE-Z-1, NUDOCS 8508260207 |
Download: ML20137F393 (6) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
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ML20076E2741991-07-0101 July 1991 Rev 0 to Hope Creek Generating Station Bailey 862 Sys Logic Module Failure Data Rept,Second Quarter 1991 ML20077C4961991-04-0808 April 1991 Rev 1 to Hope Creek Generating Station Bailey 862 Sys Logic Module Failure Data Rept,First Quarter 1991 ML20067B3751991-01-0808 January 1991 Bailey 862 Sys Logic Module Failure Data Rept,Fourth Quarter 1990 ML20045G4211990-10-31031 October 1990 Nonproprietary TS Improvement Analysis for ECCS Actuation Instrumentation for Hope Creek Generating Station. ML20058F2441990-10-0101 October 1990 Bailey 862 Sys Logic Module Failure Data Rept,Third Quarter 1990 ML20059E5401990-08-21021 August 1990 Rev 2 to Removal of APRM Downscale Scram Setpoint for Hope Creek ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20086U2571989-03-31031 March 1989 Estimated Frequency of Loss of Offsite Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations ML20248D7751989-03-0909 March 1989 Rev 1 to SPDS Final Validation & Verification Rept ML20207P1011988-09-28028 September 1988 Rev 0 to SPDS Verification & Validation Program,Final Rept ML20151V1221988-04-0101 April 1988 1987 Summary Rept for Hope Creek Generating Station Salt Drift Monitoring Program ML20151A5811988-03-31031 March 1988 Reliability Summary Rept for Bailey 862 Solid State Logic Module ML20237L6171987-08-17017 August 1987 Bailey 862 Solid State Logic Module Bi-Monthly Failure Rept ML18093A1791987-06-19019 June 1987 Installation of Trip-A-Unit Protection Scheme Suppl Info Salem & Hope Creek Generating Stations. ML20209H5461987-04-15015 April 1987 Crdr Supplemental Rept III Hope Creek Generating Station ML18092B4971987-04-0303 April 1987 S-C-E500-NSE-0675-R-1, Justification for Operation of All Three Units at Artificial Island at Increased Power During Hope Creek-Keeney Line Outage. ML20204G0861987-02-12012 February 1987 Rev 0 to Hope Creek SPDS Verification & Validation Design Review Rept ML20213F8451986-11-0606 November 1986 Crdr Supplemental Rept Ii,Hope Creek Generating Station ML20215F3881986-10-0303 October 1986 Hot/Cold Loss of Power Observation Rept ML20195D1411986-05-23023 May 1986 Addendum 3 to Rev 4 to Environ Qualification Summary Rept ML20154N2251986-02-28028 February 1986 Rev 1 to Main Steam Tunnel Flooding Analysis ML20205K2001986-02-21021 February 1986 Rev 4 to Environ Qualification Summary Rept for Hope Creek Generating Station ML20151U7081986-01-31031 January 1986 Monitoring of Lng & Liquified Petrolium Gas Shipping & Const Activities on Delaware River ML20138J8351985-12-31031 December 1985 Single-Failure Analysis for Neutron Monitoring & Process Radiation Monitoring Sys ML20136J3471985-12-27027 December 1985 Control Room Design Review Supplemental Rept 1,Hope Creek Generating Station ML20136D7951985-11-30030 November 1985 Preservice Exam Limitations Rept ML20137T6711985-11-0505 November 1985 Rev 3 to Environ Qualification Summary Rept for Hope Creek Generating Station ML20209J0041985-11-0404 November 1985 Safety Evaluation PSE-SE-Z-024, Deletion of Transversing In-Core Probe Uncertainty,Test 16. Related Info Encl ML20136D6581985-10-31031 October 1985 Rev 1 to Confirmatory Reactor Bldg Basemat Analysis for Hope Creek Generating Station Pse&G ML20138G4741985-10-15015 October 1985 Safety Evaluation:Simplification of Test 23A,MSIV Functional Test ML20138N6681985-10-15015 October 1985 Single Failure Analysis for Neutron Monitoring & Process Radiation Monitoring Sys ML20138G5051985-10-15015 October 1985 Safety Evaluation:Simplification of Test 32,Reactor Water Cleanup Sys ML20138G4931985-10-15015 October 1985 Safety Evaluation:Simplification of Test 28E,Recirculation Sys Cavitation ML20138G4871985-10-15015 October 1985 Safety Evaluation:Simplification of Test 24,Relief Valves 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
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Finalized April 1999 ML20206C8481999-04-22022 April 1999 SER Authorizing Pse&G Proposed Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B Pursuant to 10CFR50.55a(a)(3)(i) LR-N990157, Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced1999-04-12012 April 1999 Special Rept 99-001:on 990315, C EDG Valid Failure Occurred During Surveillance Testing.Testing Resulted in Unsuccessful Loading Attempt,Due to Failure EDG Output Breaker to Close.Faulty Card Replaced ML20205R5901999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Hope Creek Generating Station,Unit 1.With ML20205G6051999-03-19019 March 1999 SER Accepting Relief Request Re Acme Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components,Section Xi,Div 1 ML20205F8911999-03-18018 March 1999 Safety Evaluation Authorizing Licensee Requests for Second 10-year Interval for Pumps & Valves IST Program ML20204F7951999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Hope Creek Generating Station,Unit 1.With ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20202F6861999-01-26026 January 1999 Engine Sys,Inc Part 21 (10CFR21-0078) Rept Re Degradation of Synchrostat Model ESSB-4AT Speed Switches Resulting in Heat Related Damage to Power Supply Card Components.Caused by Incorrect Sized Resistor.Notification Sent to Customers ML18107A1871998-12-31031 December 1998 PSEG Annual Rept for 1998. ML20199E7271998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Hope Creek Generating Station,Unit 1.With ML18107A1881998-12-31031 December 1998 PECO 1998 Annual Rept. LR-N980580, Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Hope Creek Generating Station,Unit 1.With ML20198N4161998-11-12012 November 1998 MSIV Alternate Leakage Treatment Pathway Seismic Evaluation LR-N980544, Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Hcgs,Unit 1. with ML20155J9861998-10-31031 October 1998 Non-proprietary TR NEDO-32511, Safety Review for HCGS SRVs Tolerance Analyses LR-N980491, Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Hope Creek Generating Station,Unit 1.With ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils LR-N980439, Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Hope Creek Generating Station Unit 1.With LR-N980401, Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Hope Creek Generating Station,Unit 1 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps LR-N980354, Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Hope Creek Generating Station,Unit 1 ML20236E9491998-06-30030 June 1998 Rev 0 to non-proprietary Rept 24A5392AB, Lattice Dependent MAPLHGR Rept for Hope Creek Generating Station Reload 7 Cycle 8 ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. 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Nuclear Business Unit Salem,Hope Creek Emergency Preparedness, 980303 1999-09-08
[Table view] |
Text
PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK PROJECT SAFETY EVALUATION No. PSE-SE-Z-001 TITLE: DELETION OF TURBINE TRIP TEST AT TEST CONDITION 3 FROM THE POWER ASCENSION TEST PROGRAM DURING CONDUCT OF TEST NUMBER 25 - TURBINE TRIP AND GENERATOR LOAD REJECTION Date: AUG 201985 1.0 PURPOSE The purpose of this Safety Evaluation is to document the results of the evaluation performed to delete the Turbine Trip Test at Test Condition 3 and change the Generator Load Rejection Test at Test Condition 1 or 2 to a Turbine Trip Test in the Power Ascension Test Program.
2.0 SCOPE The area of concern for this proposed change is the ~
adequacy of the Power Ascension Test Program.
~
3.0 REFERENCES
- 1. FSAR Chapter 14
- 2. GE Startup Test Specification No. 23A4137 Rev. 0
- 3. NRC Regulatory Guide 1.68, August 1978'.
- 4. Hope Creek Generating Station Draft Technical Specifications 2
4.0 DISCUSSION Regulatory Guide 1.68 (Revision 2, August 1978), Appendix A, paragraphs 5.1.1 and 5.n.n require that a Turbine. Trip and Generator Load Rejection to be performed at 100%
power to demonstrate that the dynamic response of the plant is in accordance with design requirements for turbi'ne trip and full load rejection. These tests may be combined if a turbine trip is initiated directly during the generator load rejection instead of tripping from secondary effects such as a turbine overspeed trip. Test Number 25, Turbine Trip and Generator Load Rejection, is currently planned to be performed at three conditions during the Power Ascension Test Program; 1) a generator PSE-SE-Z-001 1 of 3 G508260207 850821
{DR ADOCK 05000354PDR
load rejection during Test Condition 1 or 2 (within the bypass capacity of the plant); 2) a turbine trip during Test Condition 3 (approximately 75% power); and 3) a generator load rejection at Test Condition 6 (approximately 100% power). It is proposed to delete the Turbine Trip Test at Test Condition 3 and change the Generator Load Rejection Test at Test Condition 1 or 2 to a Turbine Trip Test. This proposed testing will demonstrate that Regulatory Guide 1.68 objectives are met. '
Response of the system during a turbine trip and generator load rejection is determined by analyzing test data and comparing to acceptance criteria, level 1 and-level 2, which define the required system performance.
The generator load rejection (Test Condition 6) and the turbine trip (Test Condition 1 or 2) provide data to demonstrate that the level 1 and 2 criteria are met during a turbine trip. The turbine bypass system performance will be verified at a lower power level by changing the proposed generator load rejection at Test Condition 1 or 2 to a turbine trip. Because of the enhanced data acquisition system available, integrated 3 system response to a turbine trip can be obtained from the Generator Load Rejection Test at Test Condition 6.
Control systems which regulate the long term operation -
following the transients are separately tested during the Power Ascension Test Program. Feedwater and level '
control system tuning in Test Number 21 (ST Feedwater System Response) will ensure proper water level control. High and low water level trip avoidance will be verified in the Generator Load Rejection Test at Test Condition 6. Pressure control tuning during Test Number 20 (ST Pressure Regulator testing) will ensure that the MSIV closure trip on low turbine inlet pressure is avoided during the transient.
5.0 CONCLUSION
Current testing of the generator load rejection at 100%
power, satisfies the requirements imposed by Regulatory Guide 1.68 (Revision 2), Appendix A, paragraphs 5.1.1 and 5.n.n. In addition, the proposed' Turbine Trip Test within~ bypass valve capacity (Test Condition 1 or 2) provides additional verification of the response of the protective systems and also provides demonstration of the bypass system's capability to avoid scram at low-power levels.
PSE-SE-Z-001 2 of 3
The Turbine Trip Test has been previously demonstrated to be a mild transient event and poses no serious threat to the core and reactor integrity (Reference FSAR Section 15.2.3). In addition, the transient results fron a generator load rejection at full power are more limiting than the results from a turbine trip at Test Condition 3 (Table 1).
A Technical. Specification change is not required and safety related systems or safe operation of the plant is not affected. Therefore, the changes do not involve an unreviewed safety question.
6.0 DOCUMENTS GENERATED -
NONE 7.0 RECOMMENDATIONS The FSAR and Startup Test Procedures shall be revised to reflect the changes to the Turbine Trip and Generator Load Rejection testing during the Power Ascension.
8.0 ATTACHMENTS Table 1, Startup Data Comparison 9.0 SIGNATURES Originator // ~~
/ 8 o PT
/ Date Ve rifie r % 0. qh _ C F/20/fs'
' Datd Group Head (or SSE) buttto ddt R/h/9[
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hf Ddtd ff PSE-SE-2-001 3 of 3
- s TABLR 1 STARTUP DATA COMPARISON Grand Gulf-l Kuo Sheng 1 Kuo Sheng 2 LaSalle 2 Susquehanna 1 LR TT LR TT LR TT LR TT LR TT Power / Flow 99.7 72.1 97 74 95.8 75.1 95.7 69 99.9 75 :
97.8 96.4 99.4 100 99.1 99.9 93.1 93 98.8 100 Initial Dome 1023 989 985 978 981 972 999 967 1010 980 Proesure (paig)
- Peck Dome 1111 1044 1045 1009 1052 1004 1078 1030 1075 1043 Pres. (psig)
Dome Press 88 55 60 31 71 32 79 63 81 63 (psi)
Heat Flux 0 0 0 0 0 0 0 0 0 0 (1 NBR) l I
LR = Load Rejection
! TT = Turbine Trip 1
thj
TEST NUMBER 27 - RECIRCULATION FLOW CONTROL SYSTEM TEST SIMPLIFICATION OBJECTIVE:
Regulatory Guide 1.68 ( Revision 2, Augus t 1978), Appendix A, paragraph 5.s requires that the recirculation flow control system be calibrated as necessary and performance verified, and paragraph 5.h.h requires that the dynamic response of the plant to design load swings be demonstrated to be in accordance with design. Hope Creek's Power Ascension Test Number 27, Recirculation Flow Control System, determines the plant response to changes in recirculation flow, optimizes settings of the master flow controller and demonstrates plant loading capabilities. Testing is performed along the 50%
load line between Test Conditions 2 and 3 and along the 100%
load line between Test Conditions 5 and 6 of FSAR figure 14.2-4. It is proposed to simplify the testing by reducing the number of intermediate flow conditions and testing inputs (ramp and step demands) and to delete the Automatic Load Following (ALF) testing and associated response criteria.
DISCUSSION:
Response of the system is determined by analyzing test data and comparing to acceptance criteria which define the ,
required system performance. Testing of the recirculation speed loops is performed at the 50% load line using large plus and minus step changes and the speed controller gains are optimized. After the speed loops have been optimized, the system may be switched to master manual modo and the master controller is tested to obtain acceptable response in the manual mode. Following these tests the master controller is switched to the Automatic Load Following mode (ALP) for optimization of that control loop. When the plant is tested along the 100% load line, the recirculation system is tested by inserting small plus and minus step changes in the local manual and master manual modes. The automatic load following loop is also tested by means of small load demand changes.
Prior to the power ascension test program, predictions of system behavior will be performed to aid in the tuning of the Recirculation Flow Control System. In addition to this analysis, previous test experience from similar plants will be used to provide best estimates for initial controller settings. Bench calibration of the controllers using these best estimate settings will be performed during the preoperational phase of testing. As a result of analysis and bench calibration of controllers, the number of intermediate PAGE 1 16-Aug-85
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and test inputs (ramp and step demands) required to achieve the desired system performance can be reduced. ALF testing i
and associated response criteria can be deleted since the ALF function will be disabled.
CONCLUSION:
l The subject test can be simplified by using pretest analysis l and bench calibration of controllers to minimize the number l of intermediate flow conditions and test inputs of the test.
I All criteria of the currently planned test will be satisfied (with the exception of the ALF testing which is the subject of a separate writeup), and the objectives of Regulatory Guide 1.68 (Revision 2, August 1978), Appendix A paragraphs i 5.s and 5.h.h will be satisfied. In addition, safety systems l or the safe operation of the plant is not affected. Based on j the above, the simplifications do not involve an unreviewed l
safety question. Therefore, Hope Creek's Power Ascension Test Number 27, FSAR Table 14.2-5, Recirculation Flow Control System, can be simplified using pretest analysis and bench calibration of controllers to reduce the number of l
intermediate flow conditions and test inputs (ramp and step demands).
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PAGE 2 16-Aug-85 lb