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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: Ipeees, Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML20198N4161998-11-12012 November 1998 MSIV Alternate Leakage Treatment Pathway Seismic Evaluation ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. ML18106A6681998-06-17017 June 1998 Charting the Future ML20248C7381998-05-22022 May 1998 Rev 0 to Safety Evaluation 98-015, Extension of Allowed Out of Service Time for B Emergency Diesel Generator ML18106A2571998-01-19019 January 1998 Nuclear Business Unit Future Objectives ML20216E5431997-12-31031 December 1997 Rev 1 to GE-NE-523-A164-1294, Hope Creek 1 Generating Station RPV Surveillance Matls Testing & Fracture Toughness Analysis ML20199A6791997-10-31031 October 1997 RF07 Shroud Circumferential Weld Ultrasonic Exams, Final Rept ML20249A8281997-06-0505 June 1997 100 F Sacs Design Temp Limit Evaluation ML20137M9261996-10-31031 October 1996 Monthly Indicator Rept ML20085F1221995-04-30030 April 1995 RPV Surveillance Matls Testing & Fracture Toughness Analysis ML20082V1881994-10-11011 October 1994 Investigation of an Allegation of Inadequate CR Staffing at Hope Creek Generating Station ML20069D7191994-04-30030 April 1994 Ipe ML20125D9171992-12-11011 December 1992 Simulator 4-Yr Recertification Rept ML20106E1231992-10-31031 October 1992 IPE Level II Analysis Preliminary Summary ML18096A5831992-03-31031 March 1992 Rev 1 to Estimated Frequency of Loss of Off-Site Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations 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 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 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000354/LER-1999-011, :on 990919,unplanned Inoperability of HPCI Sys Occurred Due to Failure of Trip Unit Associated with HPCI Turbine Exhaust Pressure Transmitter.Failed Trip Unit Was Replaced & Procedures Were Revised.With1999-10-19019 October 1999
- on 990919,unplanned Inoperability of HPCI Sys Occurred Due to Failure of Trip Unit Associated with HPCI Turbine Exhaust Pressure Transmitter.Failed Trip Unit Was Replaced & Procedures Were Revised.With
ML20217F1501999-10-12012 October 1999 Special Rept:On 990929,south Plant Vent (SPV) Range Ng Monitor Was Inoperable.Monitor Was Inoperable for More than 72 H.Caused by Electronic Noise Generated from Noise Suppression Circuit.Replaced Circuit ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data 05000354/LER-1999-010, :on 990831,automatic Isolation Signal Received. Caused by Steam Flashing That Resulted in Spurious Steam Line Pressure Signals.Isolation Signal Was re-set & warm-up of RCIC Steam Lines Was Completed.With1999-09-29029 September 1999
- on 990831,automatic Isolation Signal Received. Caused by Steam Flashing That Resulted in Spurious Steam Line Pressure Signals.Isolation Signal Was re-set & warm-up of RCIC Steam Lines Was Completed.With
ML20212H0711999-09-21021 September 1999 Safety Evaluation Supporting Amend 123 to License NPF-57 ML20217M0211999-09-20020 September 1999 Part 21 Rept Re Possible Deviation of NLI Dc Power Supply Over Voltage Protection Circuit Actuation.Caused by Electrical Circuit Conditions Unique to Remote Engine Panel. Travelled to Hope Creek to Witness Startup Sequence of DG 05000354/LER-1999-009, :on 990820,license Condition Violation Re Min FW Temp Limits Were Noted.Caused by Lightning Strike. Recovered & Restored Plant Sys Affected by Electrical Transient1999-09-20020 September 1999
- on 990820,license Condition Violation Re Min FW Temp Limits Were Noted.Caused by Lightning Strike. Recovered & Restored Plant Sys Affected by Electrical Transient
ML20212C1251999-09-17017 September 1999 Safety Evaluation Supporting Amend 122 to License NPF-57 05000354/LER-1999-008-01, :on 990817,CR Was Notified That Control Equipment Mezzanine (CEM) Floor Drain Discovered in Open Position.Caused by Failure to Include CEM Floor Drain Valve in Tagging Control Sys.Valve Was Closed.With1999-09-16016 September 1999
- on 990817,CR Was Notified That Control Equipment Mezzanine (CEM) Floor Drain Discovered in Open Position.Caused by Failure to Include CEM Floor Drain Valve in Tagging Control Sys.Valve Was Closed.With
ML20211N5531999-09-0808 September 1999 Safety Evaluation Supporting Amend 121 to License NPF-57 ML20211B3781999-08-13013 August 1999 Special Rept 99-002:on 990730,NPV Radiation Monitoring Sys Was Declared Inoperable.Caused by Voltage Induced in Detector Output by Power Cable to Low Range Sample Pump. Separated Cables & Secured in Place to Prevent Recurrence ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8331999-07-26026 July 1999 Safety Evaluation Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given HCGS Design,Operation & History ML20216D8721999-07-26026 July 1999 Review of Submittal in Response to USNRC GL 88-20,Suppl 4: Ipeees, Fire Submittal Screening Review Technical Evaluation Rept:Hope Creek Rev 1:980518 ML20210F3331999-07-22022 July 1999 Safety Evaluation Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3.Finds That Proposed Alternative for RR-B3 Provides Acceptable Level of Quality & Safety & Authorizes Alternative Pursuant to 10CFR50.55a(a)(3)(i) 05000354/LER-1999-007-01, :on 990614,license Condition Violation - Class 1E Battery Charging Operation Was Noted.Caused by Inadequate Procedure Development.Procedures Revised & Personnel Held Accountable for Inappropriate Actions1999-07-14014 July 1999
- on 990614,license Condition Violation - Class 1E Battery Charging Operation Was Noted.Caused by Inadequate Procedure Development.Procedures Revised & Personnel Held Accountable for Inappropriate Actions
ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8901999-06-30030 June 1999 IPEEEs Technical Evaluation Rept High Winds,Floods & Other External Events ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept 05000354/LER-1999-006-01, :on 990518,unexpected Actuation of B Channel PCIS Occurred.Caused by Personnel Error.Addl Training Will Be Provided to Operations Personnel to Preclude Addl Unexpected ESF Actuations1999-06-15015 June 1999
- on 990518,unexpected Actuation of B Channel PCIS Occurred.Caused by Personnel Error.Addl Training Will Be Provided to Operations Personnel to Preclude Addl Unexpected ESF Actuations
ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML20196A1511999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Hope Creek Generating Station,Unit 1.With ML20206Q4731999-05-14014 May 1999 SER Accepting Response to GL 97-05, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). Finalized April 1999 ML20206U1571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With 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) 05000354/LER-1999-005, :on 990324,TS Prohibited Condition Re Inadequate Secondary Containment Surveillance Tests,Was Noted.Caused by Personnel Error.Performed Design Calculation GU-0030 & Revised Procedure HC.OP-ST.GU-002.With1999-04-21021 April 1999
- on 990324,TS Prohibited Condition Re Inadequate Secondary Containment Surveillance Tests,Was Noted.Caused by Personnel Error.Performed Design Calculation GU-0030 & Revised Procedure HC.OP-ST.GU-002.With
ML20205R8721999-04-19019 April 1999 Safety Evaluation Supporting Amend 120 to License NPF-57 ML18107A1791999-04-15015 April 1999 Safety Evaluation Supporting Changes to QA Program in That QA Program Continues to Meet Requirements of App B to 10CFR50 ML20205P7701999-04-14014 April 1999 Safety Evaluation Supporting Amend 119 to License NPF-57 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 ML20205G3781999-03-0909 March 1999 Safety Evaluation Supporting Amend 117 to License NPF-57 05000354/LER-1999-002, :on 990206,discovered That Flowpath Verification for B Safety Auxiliaries Cooling Sys Had Not Been Performed.Caused by Personnel Error.Performed Flowpath Verification.With1999-03-0202 March 1999
- on 990206,discovered That Flowpath Verification for B Safety Auxiliaries Cooling Sys Had Not Been Performed.Caused by Personnel Error.Performed Flowpath Verification.With
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 ML20203F8861999-02-10010 February 1999 Safety Evaluation Supporting Amend 115 to License NPF-57 ML20203F7061999-02-0909 February 1999 Safety Evaluation Supporting Amend 114 to License NPF-57 ML20203C7791999-02-0404 February 1999 Safety Evaluation Supporting Amend 113 to License NPF-57 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 05000354/LER-1997-016-01, :on 970716,filtration,recirculation & Ventilation Sys TS Surveillance Compliance Occurred.Caused by Failure of Procedure Revs to Recognize Need to Justify Exception.Procedures Revised.With1999-01-0606 January 1999
- on 970716,filtration,recirculation & Ventilation Sys TS Surveillance Compliance Occurred.Caused by Failure of Procedure Revs to Recognize Need to Justify Exception.Procedures Revised.With
ML20199E7271998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Hope Creek Generating Station,Unit 1.With ML18107A1871998-12-31031 December 1998 PSEG Annual Rept for 1998. ML18107A1881998-12-31031 December 1998 PECO 1998 Annual Rept. 05000354/LER-1998-008-02, :on 981115,ESFA Automatic Reactor Scram, Occurred.Caused by High Moisture Separator Level.Moisture Separator Drain Tank Dump Valves Were Tested Satisfactorily While Shutdown & Again During Restart1998-12-15015 December 1998
- on 981115,ESFA Automatic Reactor Scram, Occurred.Caused by High Moisture Separator Level.Moisture Separator Drain Tank Dump Valves Were Tested Satisfactorily While Shutdown & Again During Restart
1999-09-08
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK PROJECT SAFETY EVALUATION No. PSE-SE-2-002 TITLE:
DELETION OF AUTOMATIC LOAD FOLLOWING TESTING FROM THE POWER ASCENSION TEST PROGRAM Da te :
NE20M 1.0 PURPOSE The purpose of this Safety Evaluation is to document the results of the evaluation performed to delete testing the Automatic Load Following (ALF) capability of the reactor from the Power Ascension Test Program.
2.0 SCOPE Automatic Load Following capability is a part of the Recirculation Flow Control system which is a subsystem of the Reactor Recirculation system.
3.0 REFERENCES
1.
FSAR Chapter 14 2.
GE Startup Test Specification No. f.3A4137 Rev. 0 3.
NRC Regulatory Guide 1.68 - Revision 2, August 1978 4.
Hope Creek Generating Station D; aft Technical Specifications 4.0 DISCUSSION Regulatory Guide 1.68 (Revision 2, August 1978), Appendix A,
paragraph 5.h.h requires that the dynamic response of the plant to design load swings be demonstrated and shown to be in compliance with design and paragraph 5.s requires calibration and verification of the performance of major plant control systems.
Testing of the Automatic Load Following (ALP) capability of the reactor is currently planned to be performed during the following control system tuning tests specified in Hope Creek's FSAR Table 14.2-5: Test Number 20 - Pressure Regulator, Test Number 21 - Feedwater System Response (level control) and Test Number 27 - Recirculation Flow Control System.
It is proposed to delete ALF mode testing during these tests.
8508260198 850821 DR ADOCK 05000354 PDR PSE-SE-2-002 1 of 2
s.
Acceptance criteria require that the system response to step changes in system inputs while operating in the ALF mode be non divergent (level 1).
In addition, criteria on the power change rate and the range over which ALF is operable are defined (level 2).
The Automatic Load Following mode of operation is not-a safety related function but is instead intended to provide additional operating versatility to the utility.
The ALF mode ca'n be disabled since the system consists of non-essential equipment.
Since ALF will be disabled, the
. plant will not be subjected to load swings associated with. ALP, and no testing is required for this mode of operation.
5.0 CONCLUSION
Automatic Load Following mode of operation is not a safety related function.
Disabling of the ALF function does not require / involve any Technical Specification change (ALF is not addressed in the TS) and will not af fect any safety systems or the safe operation of the plant and therefore does 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 deletion of Automatic Load Following function testing from the Power Ascension Test Program.
9.0 SIGNATURES f
Originator !1 i ([h l u,
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TEST NUMBER 17 - CORE PERFORMANCE SUBSTITUTE TECHNICAL SPECIFICATION SURVEILLANCE i
O BJECTIVE :
Regulatory Guide 1.6 8 (Revision 2, Augus t 1978), Appendix A, paragraph 5.b requires that steady-state core performance to be in accordance with design throughout the permissible range of power-to-flow conditions.
Test Number 17 (FSAR Figure 14.2-5), Core Performance, evaluates the principal thermal and hydraulic parameters associated with core behavior.
These parameters include the core thermal power and flow and thermal margins.
Testing is performed at Test Cont'tions 1, 2,
3, 4, 5, and 6 of FSAR Figure 14.2-4.
It is proposed that the Plant Technical Specification Surveillance Procedures, associated with compliance to required thermal margins, be substituted for Test Number 17.
DISCUSSION:
The Plant Technical Specifications define the monitoring requirements for demonstration of compliance with thermal margins (Maximum Linear Heat Generation Rate - MLHGR, Maximum Critical Power Ratio - MCPR, and Maximum Average Planar Linear Heat Generation Rates - MAPLHGR).
The applicable Technical Specification sections (section 3/4.2.4, 3/4.2.3, 3/4.2.1) require that at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the thermal margins are verified to be within the specified limits when core thermal power is greater than or equal to 25% of rated l
thermal powe r.
In addition, within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> af ter a thermal power increase of at least 15% of rated thermal power the thermal limits must also be verified.
Complying with these Technical Specification surveillance requirements meets the l
objectives of Regulatory Guide 1.68 (Revision 2, August l
1978), Appendix A, paragraph 5.b and Test Number 17.
Plant' Surveillance Test procedures in accordance with Technical Specifications are also utilized to calibrate the Local Power Range Monitors (LPRMs) and Average Power Range Monitors (APRMs).
Together, these two plant surveillance procedures ensure that the APRM instrumentation is correctly measuring core thermal power and the demonstration of compliance to rated power is required by the plant operating license.
Tes t Number 11 ( S T-13 ), Process Computer, verifies the performance of the process computer under plant operating l
conditions.
As part of this verification, manual or off-line
)
t HCSTRPl/ TEST 19.WKS PAGE 1 16-Aug-85 j
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calculations are used to evaluate the process computer calculations for MCPR, MLHGR, and MAPLHGR.
In addition,
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manual heat balance calculations are performed to verify the accuracy of the process computer power calculation.
This tect, therefore, provides assurance that the process computer calculation for core thermal power and thermal margins are consistent with design methods.
To provide assurance that the core flow measurement system is functioning properly, two specific tests are dedicated to the 2
calibration and measurement of core flow parameters.
Test i
Number 29, Recirculation System Flow Calibration, provides a complete calibration of the installed recirculation flow I
instrumentation including specific signals to the plant process computer.
The core flow is measured by summing the flow from the individual jet pumps.
The jet pump flows are i
determined from single and double tap pressure differential i
instruments.
Recirculation drive flow, which is an input to i
rod block and scram setpoints, is determined from an elbow tap differential pressure.
The calibration of the l
instrumentation is performed at Test Condition 3 and Test l
Condition 6, of FSAR Figure 14.2.4 to ensure that the system will provide a correct core' flow indication at rated 1
j conditions.
Tes t Numbe r 28C, Recirculation System Pe rformance, records recirculation system parameters during i
the power test program (Test Conditions 2, 3,
4, and 6).
Core flow (from jet pump flow instrumentation), core pressure 3
drop, jet pump M-ratio, drive flow and recirculation pump efficiency are evaluated and compared to predicted values.
l The flow control system is also adjusted at this time to limit the maximum core flow to 102.5% of rated.
These tests, therefore, provide adequate assurance that the core flow is being measured properly.
I CONCLUSION:
i Compliance with the Plant Technical Specification Surveillance Requirements, via existing surveillance procedures, and performance of the system tests and
{
calibrations noted above will satisfy the objectives of j
Regulatory Guide 1.68 (Revision 2, August 1978), Appendix A, paragraph 5.b, as well as the requirements of Test Number 17.
Based on the above discussion, the proposed change will i
not affect any safety systems or the safe operation of the l
plant and therefore does not involve an unreviewed safety question.
Based on the above, the Plant Technical Specification Surveillance Procedures can be substituted for Test Number 17.
i 1
I HCSTRPl/ TEST 19.WKS PAGE 2 16-Aug-85 l
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