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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20217N6531999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Hope Creek Generating Station,Unit 1.With ML20210U4721999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Hope Creek Generating Station,Unit 1.With ML20210C4731999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Hope Creek Generating Station,Unit 1.With ML20196A1511999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Hope Creek Generating Station,Unit 1.With ML20206U1571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Hope Creek Generating Station,Unit 1.With ML20205R5901999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Hope Creek Generating Station,Unit 1.With ML20204F7951999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Hope Creek Generating Station,Unit 1.With ML20199E7271998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Hope Creek Generating Station,Unit 1.With 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 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 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 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 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 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 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 LR-N980104, Monthly Operating Rept for Feb 1998 for Hope Creek Generating Station,Unit 11998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Hope Creek Generating Station,Unit 1 ML20203B6741998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Hope Creek Generation Station,Unit 1 ML20198T3591997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Hope Creek Nuclear Generating Station,Unit 1 ML20203B6841997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 & Jan 1998 for Hope Creek Generation Station,Unit 1,summary of Changes,Tests & Experiments ML20198T4061997-11-30030 November 1997 Revised MOR for Nov 1997 for Hope Creek Nuclear Generating Station,Unit 1.Summary of Changes,Tests,Experiments & Refueling Info,Encl ML20203K3751997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Hcgs,Unit 1 ML20203K3821997-10-31031 October 1997 Revised Monthly Operating Rept for Oct 1997 for Hcgs,Unit 1 ML20199G5591997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Hcgs,Unit 1 ML20199G5931997-09-30030 September 1997 Revised Monthly Operating Rept for Sept 1997 for HCGS, Unit 1 ML20211Q6481997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Hope Creek Generating Station ML20212A5301997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Hope Creek Generating Station,Unit 1,summary of Changes,Tests & Experiments ML20217A1491997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Hope Creek Generating Station,Unit 1 ML20217A6261997-07-31031 July 1997 Revised Monthly Operating Rept for Jul 1997 for Hope Creek Generating Station,Unit 1 LR-N970503, Monthly Operating Rept for Jul 1997 for Hope Creek Generating Plant Unit 11997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Hope Creek Generating Plant Unit 1 ML20149F2921997-06-30030 June 1997 Monthly Operating Rept for June 1997 for HCGS ML20149F3061997-05-31031 May 1997 Revised Monthly Operating Rept for May 1997 for Hope Creek Generating Station.Summary of Changes,Tests & Experiments Encl ML20140H6761997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Hope Creek Generating Station Unit 1.Summary of Changes,Tests & Experiments Implemented in Apr 1997 Included in Rept LR-N970321, Monthly Operating Rept for Apr 1997 for Hope Creek Generating Station1997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Hope Creek Generating Station ML20137X7311997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Hope Creek ML20147F6051997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Hope Creek Generating Station ML20147F6111997-01-31031 January 1997 Revised MOR for Jan 1997 for Hope Creek Generating Station LR-N970110, Monthly Operating Rept for Jan 1997 for Hope Creek Generation Station Unit 11997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Hope Creek Generation Station Unit 1 ML20133M9831996-12-31031 December 1996 Monthly Operating Rept for Dec 1996 for Hope Creek Generating Station ML20133B7901996-11-30030 November 1996 Monthly Operating Rept for Nov 1996 for Hope Creek Generation Station Unit 1 LR-N966376, Monthly Operating Rept for Oct 1996 for Hope Creek Generation Station Unit 11996-10-31031 October 1996 Monthly Operating Rept for Oct 1996 for Hope Creek Generation Station Unit 1 ML20129A8271996-09-30030 September 1996 Monthly Operating Rept for Sept 1996 for Hope Creek Generation Station Unit 1 ML20134C0941996-08-31031 August 1996 Monthly Operating Rept for Aug 1996 for Hope Creek Generation Station ML20116P0181996-07-31031 July 1996 Monthly Operating Rept for Jul 1996 for Hope Creek Unit 1 ML20117C3331996-07-31031 July 1996 Monthly Operating Rept for July 1996 for Hope Creek Generation Station Unit 1 ML20134C1031996-07-31031 July 1996 Revised Monthly Operating Rept for Jul 1996 Hope Creek Generation Station ML20115E8491996-06-30030 June 1996 Monthly Operating Rept for June 1996 for Hope Creek Generation Station ML20117C3701996-06-30030 June 1996 Revised Monthly Operating Rept for June 1996 for Hope Creek Generating Station ML20116P0381996-06-30030 June 1996 Summary of Changes,Tests & Experiments That Had Been Implemented During June 1996 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
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I DOCKET NO.: 50-354 U!JI T : ljope Creek DATE: 12/11/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445 SXt@LARY OF CHMLQERuT_EATLAUp EXEERIMENTS EQB_IliluiME._SRREIL9EIM RATlH9_.1TATI ON MONTH DI MMDER 1997 and._Lang ry 1998 The following items completed during December 1997 and January 1998 have been evaluated to determine:
- 1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or
- 2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or
- 3. If the margin of safety as defined in the basis for any technical specification is reduced.
The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
D_eJ!.Lgp Citangp_s S3gnmarv .qf Saf ety Evaluations 4EC-3449, Pkg. 6, Replace Selected Carbon Steel Piping and Fittings with Chromium Alloy Due to Flow Accelerated Corrosion.
This design change addressed various fittings and pipe that need to be replaced due to Flow Accelerated Corrosion. The following systems are covered by the safety evaluation associated with this design change: Feedwater, Condensate, Seal Steam, Moisture Separator Drains, Plant Heating, Main Steam, Extraction Steam, Heater Drains, Condensate Air Removal, and Reactor Feed Pump Turbine Steam. The design change includes replacing carbon steel piping and fittings with chrome moly alloy steel material of equal or heavier wall thickness.
9002240397 980215 PDR ADOCK 05000354 R PDR
, )4 This design change did not increase'the probability or ;
consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce ,
the margin of safety for any Technical Specifications, i Therefore, there are no unreviewed safety questions associated !
with this design change.
Tomocrary Modifications Summary of Safety Ey_glug_t;1 gag There were no changes in this category implemented during >
December 1997 or January 1998.
Procedures Summary _of_ Safety EvaluatioD1 ,
NC.DE-AP.ZZ-0004(Q), Rev. 5, Design Drawings. This procedure revision included responsibility changes in the process for controlling engineering design drawings. This procedure revision allowed the task of transferring approved design change information-to be performed by a drafter or a designer.
Previously, this work was performed only by designers. This procedure revision also includes supervisory title changes. ;
The changes included in this procedure are considered to be administrative in nature. Additionally, a designer will continue to peer review the changes to the engineering drawings.
Therefore, this procedure revision did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety questions associated with this procedure revision.
UfSAB_ chance Notices Summary of Safety EvaluatigJ13 CN M97-064, NBU Organization Changes, Consolidation of Manger - !
Emergency Preparedness Position with the Managers - Corrective Action and Instructional Technology. This UFSAR change notice consolidates the Manager - Emergency Preparedness position with the Managers - Corrective Action and Instructional Technology.
The-new title is Manager - Corrective Action, Emergency Preparedness, and Instructional Technology. The manager reports to the Director - Quality,-Nuclear Training, and Emergency Preparedness. . This change also transfers quality services functions from the Manager - Corrective Actions to the Director -
Quality, Nuclear Training, and Emergency Preparedness, 2 a
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o . ,
t l There is no reduction in the level of quality asuuran - u .<
technical support as a result of this change. Thes' te l urganizational changes only, and do not affect anv ' :u > <;9e !
l systems, or components as d Jeribed in the SAR. 'F V e > s , '
. I j UFSAR change did not increase the probability or t. .astaf e1 ena .
a malfunction of equipment important to safety, cre)?0 cht i possibility of an accident or malfunction of a diffucgg 5ype ,
than previously evaluated in the SAR, or reduce thu e.argin of l
- safety for any Technical Specifications. Therefore, there are no i i unreviewed safety questions associated with this UFSAR-change.
i CN H97-068, Safety Auxiliaries Cooling System T.asponse to a Turbine Auxiliaries Cooling System Pipe Break in a Design Basis 4
Earthquake. This UFSAR change notice was initiated to l
l incorporate the results of a calculation into the UFSAR. The calculation was performed to evaluate the Safety Auxiliaries ;
Cool.ing System (SACS) response to a Turbine Auxiliaries cooling
~
System (TACS) pipe break during a design basis earthquake. The '
calculation was required because the SACS to TACS isolation
, valves are not seismically qualified.
4 The-calculation determined that the SACS to TACS supply valves
- would automatically isolate and would support the safe shutdown
~
of the plant during design basis earthquake scenarios. This UFSAR change did not increase the probability or consequences of
, a malfunction of equipment important to safety, create the !
possibility of an accident or malfunction of a different type 1 than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no ;
unreviewed safety questions associated with this UFSAR change.
t ,
CN H97-083, Safety and Turbine Auxiliaries cooling System -
Required Flow Rates and Heat Loads. This UFSAR change notice was initiated to update the Safety and Turbine Auxiliaries Cooling i system flow rates and heat loada based on the results of a i calculation.
9
. The calculation revision analyzed the minimum requiled flow ra'.es delivered to the Safety Auxiliaries Cooling System (SACS) '
cpmponenets to ensure that they remove their as-built design heat loads and does not make any changes to system equipment or !
operation.
Therefore, this UFSAR change did not increase the probability or consequences of a malfunction of equipment j~ important to safety, create-the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical ,
Specifications. Therefore, there are no unreviewed safety questions associated with this UFSAR change. '
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l
.CN M97-004, Pcat-Scram Mechanical Vacuum Pump Operation. This UFSnR change notice revised the process for placing the '
mechanical vacuum pumps in operation after a reactor scram. Tne ;
change notice clarified the limitations for using the mechanical !
vacuum pumps anu achieved consistency between the licensing basis ,
and the operating procedures.
An engineering evaluation was also performed in conjunction with ,
this change notice. The engineering evaluation concluded that :
there would be no increase in radiological consequences or in off-site dose releases. This UFSAR change did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or ,
malfunction of a different type than previously evaluated in the ;
SAR, or reduce the margin of safety for any Technical ;
Specifications. Therefore, there are no unreviewed safety ;
questions associated with this UFSAR change. t CN M90-001, Condensate and Reactor Coolant System Chemistry Silica Limit. This UFSAR change notice raised the condensate and ;
reactor coolant system silica limit from 20 ppb to 500 ppb. This <
change is consistent with current EPRI guidance for BWR Water e Chemistry. This UFSAR change did not increase the probability or consequences-of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce l the margin of safety for any Technical Specifications. !
Therefore, there are no unreviewed safety questions associated ,
with this UFSAR change.
CN M98-005, Nuclear Business Unit Organization Change. This change notice established a new position, the Executive Vice ;
President - Nuclear Business Unit. The individual holding this s position assumes the duties and responsibilities of the Chief Nuclear Officer / President - Nuclear Business Unit in his absence.
This UFSAR change notice is organizational only and does not '
impact any system, structure, or component. This UFSAR change .
sdi d not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an i accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any .
Technical Specifications. Therefore, there are no unreviewed safety questions associated with this UFSAR change. l
-CN H98-006, Monthly Operating Report Contents. This change notice incorporated Generic Letter 97-02, was written to inform licensees that-the NRC was requesting the submittal of less .'
information in the monthly operating report. The Generic Letter allows the use of guidance provided in the Generic Letter instead of providing the information requested by Reg Guide 1.16. This 1 proposal-allowed Hope Creek to comply with Generic Letter 97-02
~instead-of Regulatory Guide 1.16.
= - . . . - ...- - ..- ,.- - -. - u.- - - ._. ---. _ .,. - - .-.- _
This proposal discusses reporting requirements only and does not impact any system, structure, or component. This UFSAR change did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident os malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety questions associated with this UFSAR change.
Reliciency Rpports Enamary of Safety Evaluations 971009231, Ultrasonic Test Scanner Bearing cap - Potential Lost Part. This deficiency report was written to document an ultrasonic test scanner bearing cap that was postulated to have fallen into the reactor, The following safety and operational concerns for the potential migration patterns in the core were addressed in the safety evaluation associated with this deficiency reports potential for control rod interference, potential for corrosion or chemical reaction with other reactor materials, potential for interference with Reactor Water cleanup (RWCU)/ Residual Heat Removal (RHR) isolation valvea, potential for fretting of fuel cladding, potential for impact to recirculation system performance, potential for blockage of vessel bottom head drain, and potential for damage to RWCU/RHR pumps.
The safety evaluation determined that the ultrasonic test scanner bearing cap would not affect safety related plant responses, including the ability to scram the control rods. Therefore, this deficiency report did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications.
Therefore, there are no unreviewed safety questions associated with this deficiency report.
971016131, Jet Pump Sensing Line Lower Bracket Clamp Repair 2 This deficiency report was written to document weld indications on three Jet Pump Sensing Line lower brackets. No cracks have been observed on the sensing lines. The safety evaluation associated with this deficiency report justified operation with a repair to the brackets. The repair consisted of clamping the sensing lines to the lower support-brackets in the original welded position, essentially restoring the lines to their original structural configuration.
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The addition of the clamps does not affect jet pump structural integrity and does not change the blowdown path during a loss of coolant accident. The sensing line is not safety related. The clamps are passive devices that restore the structural integrity of the sensing line attachments. Therefore, this deficiency report did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility ot an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical Specifications. Therefore, there are no unreviewed safety questions associated with this deficiency report.
971127121, Adjustment to Reactor Water Cleanup Leak Detection Betpoint. This deficiency report was written to document a new setpoint and allowable value for the Reactor Water Cleanup (RWCU) differential flow trip. A new design calculation was performed that required a lowering of the setpoint and the allowable value.
The calculation was performed to address the impact of a RWCU flow orifice being installed backwards.
No equipment was modified or introduced as a result of this deficiency report. This deficiency report did not increase the probability or consequences of a malfunction of equipment important to safety, create the possibility of an accident or malfunction of a different type than previously evaluated in the SAR, or reduce the margin of safety for any Technical specifications. Therefore, there are no unreviewed safety questions associated with this deficiency report.
Qther Summary of sal 9tv Evaluation There were no changes in this category implemented during December 1997 or January 1998.
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