|
---|
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 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 ML20125D9171992-12-11011 December 1992 Simulator 4-Yr Recertification Rept 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 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
MONTHYEARML20217F1501999-10-12012 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 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With 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 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) 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 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 ML20206U1571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With ML20216D8451999-04-30030 April 1999 Rev 1, Submittal-Only Screening Review of Hope Creek Unit 1 IPEEE (Seismic Portion). 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. ML18106A6681998-06-17017 June 1998 Charting the Future. LR-N980302, Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Hope Creek Generating Station,Unit 1 ML20248C7381998-05-22022 May 1998 Rev 0 to Safety Evaluation 98-015, Extension of Allowed Out of Service Time for B Emergency Diesel Generator LR-N980247, Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Hope Creek Station, Unit 1 LR-N980196, Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Hope Creek Generating Station,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML18106A5851998-03-0303 March 1998 Emergency Response Graded Exercise,S98-03. Nuclear Business Unit Salem,Hope Creek Emergency Preparedness, 980303 1999-09-08
[Table view] |
Text
O PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK PROJECT SAFETY EVALUATION No. PSE-SE-2-020 TITLE:
SIMPLIFICATION.OF POWER ASCENSION TEST NUMBER 20, PRESSURE REGULATOR Date: SEP 2 51985 1.0 PUR POSE The purpose of this Safety Evaluation is to document the results of the evaluation performed to ensure that deletion of the pressure regulator tests at Test Condition 4, the backup pressure regulator takeover testing at Test Condition 5, and the automatic load following mode tests at Test Conditions-3 and 6 from the Hope Creek power ascension test program will not adversely affect reactor, safety.
.2.0 SCOPE
~
3 The area of concern for this proposed change.is the adequacy of Hope Creek 's power ascension tes t program.
3.0 REFERENCES
1.
- 2. Regulatory Guide 1.68, Revision 2, August 1978 Hope Creek Final Safety Analysis Feport (FSAR)
Chapter 14
- 3. General Electric Startup Specification, 23A4137 Revision 0
- 4. Hope Creek Generating Station Draft Technical Specifications
- 5. Draft Hope Creek Power Ascension Test Number TE-SU.BB-221, Pressure Regulator Test - Control valves Controlling
- 6. Draft Hope Creek Power Ascension Test Number TE-SU.BB-223, Pressure Regulator Test - Bypass Valves Controlling i
PSE-SE-2-020 1 of 3 h
A DOC pp
$, ?
4.0 DISCUSSION Regulatory Guide 1.68 (Revision 2, August 1978), Appendix A, paragraphs 4.u and 5.s require demonstration of the operability of the pressure regulator system during low power testing and its calibration and performance verification 20, during power ascension testing. Test Number Pressure Regulator, determines the response of the system to rapid pressure setpoint changes in order to optimize regulator settings . Also, at specified test conditions, the load limit setpoint will be set so that the transient is handled by control and/or bypass valves.
Performance of the Pressure Regulator test is planned for Test Conditions 1 through 5. It is proposed to delete the pressure regulator tests at Test Condition 4,
the backup pressure regulator takeover testing at Test Condition 5 and the automatic load following mode tests at Test Conditions 3 and 6.
Deletion of all Test Condition 4 testing is justified in Safety Evaluation PSE-SE-2-008. Deletion of automatic load following mode tests is justified in Safety Evaluation PSE-SE-2-002.
,~Takeove.r testing of the.b.ackup' pressure regulator is currently 3, 5, and 6.
pla'nned to be per' formed at Test Conditions 2, Takeover testing a t . Test Condition 5 is bounded by testing a t Tes t Conditions 2, 3, and 6'(See Attachment 1). Thus, testing at Test Conditions 2, 3, and 6 adequately demonstrates the capability of the backup pressure regulator to control pressure in the event of a failure of the controlling pressure regulator.
Furthermore, all other tests of the pressure regulators regulators at Test Condition 5, some of which subject the to transients as severe or more severe than a failure of the controlling regulator, will be performed so that the behavior of the regulators at Test Condition 5 will be adequately determined.
5.0 CONCLUSION
S Deletion of Test Condition 4 and automatic load following mode testing was previously addressed and was found not to involve unreviewed safety questions. Deletion of takeover testing of the backup pressure regulator at Test Condition 5 does not adversely affect any safety systems or safe operation of the plant and, therefore, also does not involve an unreviewed safety question.
No Technical PSE-SE-2-020 2 of 3 1
.. o l Specifications changes are required. The remaining ;
testing meets the requirements of Regulatory Guide 1.68 '
(Revision 2, August 1978), Appendix A, paragraphs 4.u and 5.s. The Pressure Regulator test can therefore be simplified by deleting the portions of the test as discussed above.
6.0 DOCUMENTS GENERATED None 7.0 RECOMMENDATIONS Revisions to power ascension test procedures and the Hope Creek FSAR shall be made to reflect the simplification of the Pressure Regulator test described above.
8.0 ATTACHMENTS Hope Creek's Operational Power / Flow Map.
9.0 SIGNATURES Originator ~
<2 #s7pf f5&
x -
' Da'te .
Verifier </:7 L .kj -
- /2f/9C Group Head (or SSSI /fA m% f /5-SystemsAnalysisGroupHead[. h b bH).O Y/ /6 Site Engineering Manager ~
N 'l [
Datf PSE-SE-2-020 3 of 3
ATTACHMENT 1 NUCLEAR ENERGY 2 m 137 2
SUSINESS OPERATIONS - GENERAL $ ELECTRIC Rev 0 140 130 130 -
110 -
A. NATURAL CIRCULATION 1e9 "
- 8. 800N6440M REClRCULATION PuesP MED C. ANALYTICAL LouutR LatelT OF %y IIASTER POtutR Plow CONTROL g - D. ANALYTICAL UPPER LiedIT OF GIASTER POuutR PLOut COesTROL 4 .
ff 5 N
m /
e
( #
A GS -
TC4 l,
. f TC3
,# i 4 m =
TQ 006414000d PouutR LINE a= TYPSCAL STARTUP PATN d CAv TATioN REcioN 0 ' ' ' ' ' ' '
e to a ao do ao es a ao es too 110 i PEACENT CORE PL0gu
. Figure 1. Operational Power / Flow Map ase eern enev. iefei
__ ,- _ , _ . . _ . , - _ ~ _ _ . . - - _ _ , . , _ _ _ _ _ - _ _ _ _ _ _ . _ - , _
}
4 TEST, NUMBER 20 - PRESSURE REGULATOR TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS OBJECTIVE:
Regulatory Guide 1.68 (Revision 2; August 1978), Appendix A, paragraphs 4.u and 5.s require demonstration of the operability during low power testing and calibration and performance verification during power ascension testing of the pressure regulator system. Test Number 20, Pressure Regulator, determines the response of the system to rapid pressure setpoint changes and at specified test conditions the load limit setpoint will be set so that the transient is handled by control and/or bypass valves. Backup pressure regulator takeover will be tested by simulating a failure of the selected pressure regulator and regulator settings will be optimized.
Performance of this test is planned for Test Conditions 1-6.
It is. proposed to delete the pressure regulator tests and Test Condition 4, the backup pressure regulator takeover testing at Test Condition 5 and the automatic load following mode tests at Test Conditions 3 and 6.
EDI'SCUSSION:- ~
Acceptance criteria, level 1, level 2, and level 3, specify acceptable performance of the pressure regulator system.in response to testing perturbations. Level 1 and 2. criteria require that the transient response of any pressure control system-related variable to any test input must be non-divergent. Further, level 2 criteria require that the pressure response time for pressure setpoint changes and the pressure control system deadband or delay be small enough to produce steam flow variations within prescribed limits. Also, the level 2 criteria require that peak values for neutron flux and vessel pressure during the pressure regulator failure transients do not exceed prescribed limits.
The automatic load following (ALF) mode of operation of the pressure regulator system is not a safety related function but is instead an operational improvement. Since it consists of non-essential equipment, the ALF mode may be disabled and no testing of the ALF mode is required for the pressure regulator system (PSE&G Safety Evaluation No. PSE-SE-2-002, Deletion of Automatic Load Following Testing from the Power Ascension Test Program, August 10, 1985, Reference 1).
Test Condition 4 is in the region of natural circulation, and current plant Technical Specifications do not allow continued operation at this condition. Since this condition is not an intended mode of operation, the testing can be deleted (GE Technical Evaluation, " Natural Circulation Operation, Delete Test Condition", Reference 2). The objectives and requirements of Regulatory Guide 1.68, paragraphs 4.u and 5.s are still satisfied with the remaining testing.
1
/ .
1 Testing of the backup pressure regulator is performed by simulating the failure of a selected pressure regulator. This test is currently planned to be performed at Test Conditions 2, 3, 5, and 6. Testing at Test Conditions 2, 3, and 6 provides adequate demonstration of the capability of the backup pressure regulator to control pressure in the event of a failure of the controlling pressure regulator.
Prior to the power ascension test program, predictions of system behavior are performed to aid in the tuning of the pressure regulator. control system. In addition to this analysis, previous test experience from similar plants provides best estimates for initial controller settings. Bench calibrations of the controllers using these best estimate settings will be performed during the preoperational phase of testing. As a result of the analysis and bench calibration of controllers, the number of test conditions required to achieve the desired system performance can be reduced.
CONCLUSION:
Since the ALF feature is being disabled, deletion of testing of the pressure regulator system..in the ALF' mode does not .af fec.t' any' safety related systems or the s'afe operation' of the' plant' and does not involve an unreviewed safety question. Testing of the pressure regulator system at Test Condition 4 is not required since the plant will not normally operate in this mode and plant Technical Specifications.do not allow continued operation at natural circulation conditions. Therefore, deletion of Test Condition 4 testing does not affect any safety related systems or the safe operation of the plant and does not involve an unreviewed safety question. Testing of the backup pressure regulator at Test Conditions 2, 3, and 6 demonstrates the performance of the backup system. Deleting testing of the backup pressure regulator at Test Condition 5 does not affect any safety systems or the safe operation of the plant and therefore does not involve an unreviewed safety question. Test Number 20, Pressure Regulator, can therefore be simplified by deleting the automatic load following testing at Test Conditions 3 and 6, by deleting the backup pressure regulator testing at Test Condition 5 and by deleting testing at Test Condition 4.
REFERENCES
- 1. Letter, R. L. Mittl (PSE&G) to W. Butler (NRC), " Power Ascension Program Changes Hope Creek Generating Station Docket No. 50-354", August 21, 1985
- 2. Letter, J. C. Larrew (GE) to R. Salvesen (PSE&G), Hope Creek Project Startup Test Reduction Program", GP-85-190, September 3, 1985 2
. - . . _ - - _ .. - _ - _ _ . - _ _ .__ - --_ - _ . - . _ , . - _ .