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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
[Table view] |
Text
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DOCKET NO.: 50-354 UNIT: Hope Creek l DATE: 9/05/96 l i
COMPLETED BY: L. Keolev TELEPHONE: (609) 339-3517
SUMMARY
OF CIIANGES, TESTS, AND EXPERIMENTS
, FOR THE IIOPE CREEK GENERATING STATION l MONTH AUGUST 1996 i The following items completed during July 1996 have been evaluated to determine:
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- 1. If the probability of occurrence or the consequences of an accident or malfunction of i equipment important to safety previously evaluated in the safety analysis report may be increased; or
- 2. If a possibility for an accidert or malfunction of a different type than any evaluated I 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. I j 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.
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9609250236 960912 PDR ADOCK 05000354 R PDR
1 Design Changes Summary o_f Safety Evaluations DESIGN CHANGE 4HM-00119. INSTALLATION OF LADDER STORAGE BRACKETS IN POWER BLOCK - This design change package installed storage brackets on the walls of various rooms throughout the power block. The maintenance department will utilize these racks to store temporary fiberglass ladders. The permanent installation of fiberglass ladder storage areas within the power block does not increase the likelihood of a fire in a safety related area because the ladders are not ignition sources. The ladders are not subject to spontaneous combustion. The ladders do add to the combustible loading of the rooms in which they are placed, however, the placement of the storage areas complies with the 10CFR50 Appendix R requirements regarding separation of redundant trains of safety circuits. The fire detection and suppression systems are adequate to handle the increased loading. The ladder storage area will not create a hazard or impairment to a safety related system or component. The ladder storage racks conform to the seismic II/I design considerations.
Therefore, this design change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
DESIGN CIIANGE 4HE-00039. AIR INJECT AT THE BOTTOM OF CATION VESSEL
- Intermittent air injection will be provided to the bottom of cation tank to create the proper mixing of resin and water and remove acid hide-out. The cation vessel is open to the atrnosphere and as a result there will be no pressure buildup. The change has no effect on safety-related systems, as the demineralized water system does not perform safety related functions. The intermittent air supply for this process is supplied by an existing air supply sized and designed for demineralizer backwash. Failure of the system does not compromise any safety-related systems nor prevent safe shutdown of the plant.
Therefore, this design change does not increase the probability or consequences of an accident pr'eviously described in the UFSAR and does not involve an Unreviewed Safety Question.
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UF'SAR Change Notices Summary o_f Safety Evaluations
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UFSAR CHANGE NOTICE, UFSAR SECTION 5.4.7.2.6 RESIDUAL HEAT REMOVAL l
M ANUAL ACTION - This change revises the Residual Heat Removal (RHR) system operation i description to indicate that 1BCHV-F015A(B) is throttled, as opposed to fully open, to maintain '
desired system flow during RHR Shutdown Cooling Mode, as described in the original General Electric documentation (GEK 90355). The original system design intended for the 1BCHV-F015 A(B) valve to be throttled to maintain system flow to prevent pump runout conditions.
Therefore, this change will reduce the probability of occurrence of a malfunction of equipment important to safety previously described in the SAR. Operation of the RHR system in accordance with the current operating procedures and the original system design will allow normal operation of the RHR system in the shutdown cooling mode. This change will correct the documentation deficiency which exists in the UFSAR to allow normal, reliable operation of the RHR system in the shutdown cooling mode. This change does not physically alter the plant nor does it alter operating procedures. It does not affect configuration or operation of the RHR system. Loss of shutdown cooling is discussed in UFSAR Section 15.2.9. Any malfunction of the RH.R components that could lead to a loss of the shutdown cooling function would be bounded by the total loss of shutdown cooling analysis.
Therefore, this UFSAR change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
UFSAR CHANGE NOTICE, UFSAR SECTION 5.4.8.2,' REACTOR WATER CLEAN UP SYSTEM DESCRIPTION' - This UFSAR change clarifies that only the Reactor Water Clean Up (RWCU) suction line outboard containment isolation valve (IBGHV-F004) closes as a result of the RWCU high temperature on the non-regenerative heat exchanger (NRHX) outlet isolation signal. The RWCU NRHX Outlet Temperature High isolation protects the system filter /demineralizer (F/D) resins from high temperature water that could degrade the resins. In the event of a malfunction that led to a high temperature condition, a single failure of the outboard isolation valve to close could expose the resin to a high temperature. However, the RWCU F/D and associated resins are not important to safety and are not required to achieve or maintain safe shutdown of the plant. RWCU F/D resin damage due to high temperature is not included in any ;
operational transients or postulated design basis accidents previously evaluated in the SAR. The RWCU NRHX Outlet Temperature High Isolation does not serve a safety function for reactor j coolant pressure boundary or primary containment isolation or leak detection. The primary ;
containment isolation of the RWCU suction line are important to safety, however, this i clarification of documentation for the RWCU NRHX Outlet Temperature High isolation has no effect on the safety related functions of the valve. It is not discussed in the UFSAR for mitigation of any analyzed accident. This change does not alter the plant or procedures, nor does it affect any initiating events or initial condition assumptions in the S AR.
Therefore, this UFSAR change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question. !
UFSAR CHANGE, SECTION 6.3.2.2.6, 'ECCS DISCH ARGE LINE FILL NETWORK' - I This change revises UFSAR section 6.3.2.2.6 to reflect the use of the Condensate Storage and m
Transfer (CST) sy:; tem to provide ECCS keepfill, thereby allowing the removal of an ECCS
[
jockey pump from service without affecting the availability of the supported equipment. The purpose of the ECCS and RCIC fill networks is to maintain the ECCS and RCIC pump discharge lines full of water when the systems are in standby lineup in order to 1) prevent water hammer, j and 2) minimize injection time when the systems receive automatic initiation signals. The HPCI and RCIC jockey pumps are also used to maintain a water seal in the feedwater lines following a >
I LOCA. The change addresses only the keepfill networks for RCIC and ECCS. Consequently, it j does not impact or affect any precursors to accidents previously evaluated in the UFSAR and j therefore does not increase the probability of those accidents. The consequences of a failure of a j single RCIC or ECCS keepfill network are bounded by the single failures presently assumed in the
. UFSAR. When ajockey pump is removed from service, it is done so in accordance with station i administrative controls which ensure that the impact on system operability is assessed and '
l appropriate compensatory actions are considered and implemented. This, together with the -
j limitation that only a single jockey pump will be removed from service at a time, provides l reasonable assurance that a malfunction that is more limiting than that assumed in the UFSAR is -
i not made credible by the change. Although the CST system is non-safety related and non-seismic, l the check valves, isolation valves and all downstream piping supplying each ECCS and RCIC
- i discharge header are safety ielated. This would therefore prevent a failure in the CST system from propagating into the ECCS or RCIC system. Therefore, the vulnerability of plant systems to .
- a seismic event is not impacted by the change.
i l Therefore, this UFSAR change does not increase the probability or consequences of an accident j previously described in the UFSAR and does not involve an Unreviewed Safety Question.
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, UFSAR CHANGE. SECTION 9.2. ULTIMATE HEAT SINK - UFSAR Section 9.2 is being changed to clarify how the ultimate heat sink (UHS)is monitored. The UHS temperature is ,
j defined as the ' average river water temperature'. Currently, the ' average river water temperature' j can be measured two ways: 1) using the service water intake structure (SWIS) river temperature l detectors, which are two pipes - each containing a 29.5 foot RTD device with the RTD element at a the bottom of the device - installed in front of the SWIS; 2) using the service water (SW) pump l
} discharge temperature detectors, which consist of an RTD in a metal thermal well installed in the j service water piping attached to the discharge side of the service water strainers. The ' Service
!. Water Hydraulic Analysis' determines UHS temperature based upon the temperature of the water i entering the Safety Auxiliary Cooling System (SACS) heat exchanger. The SW pump discharge
] temperature reflects the temperature of the water entering the SACS heat exchanger. Monitoring j the UHS temperature at this location accounts for the heat input due to work from the SW pump.
! In addition, the change will not alter the original system configuration but will improve the system 1 description by eliminating the reference to the SWIS river temperature detectors.
I Therefore, this UFSAR change does not increase the probability or consequences of an accident
} previously described in the UFSAR and does not involve an Unreviewed Safety Question.
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Procedures Summary of Safety Evaluations j PROCEDURE CHANGE, ABNORMAL SERVICE WATER PROCEDURE CHANGE, I HC.OP-AB.ZZ-0122(Q) - The maximum allowable Ultimate Heat Sink (UHS) temperature is I defined in Technical Specification (TS) 3/4.7.1.3(b) and will allow plant operation up to a maximum river temperature of 88.6 degrees Fahrenheit. Preliminary calculations havc identified a bounding case that was not included in the analysis that determined the existing UHS upper temperature limit.
In accordance with the NRC Generic Letter (GL) 91-18, this condition is defined within section 4.4,
' Discovery Of An Existing But Previously Unanalyzed Condition or Accident' The proposed procedural changes and operation action will be consistent with the 'GL 91-18 direction to put the !
plant in a safe condition. A reasonable assurance of safety, as defined in paragraph 4.6 of GL 91-18, I can be established based on the redundant equipment availability, the low probability of occurrence and the proposed compensatory measures including administrative controls.
The current analysis has determined that all design and licensing bases can be satisfied with a lower UHS temperature for the new bounding case. The final UHS maximum temperature will be determined based on completion of extensive thermal and hydraulic calculations. Until these calculations are finalized, the allowable UHS temperature will be controlled administratively using a conservative limit that bounds all Design Basis Accidents (DB A) and normal operating cases.
The need for a permanent TS change will be determined after the calculations are finalized.
The administrative UHS temperature limit for the DBA will require additional operator action during the DBA. These additional operator actions following the DBA will be contained in the SW abnormal operating procedure. The intent of the procedure changes is to optimize the available SW flow across the Safety Auxiliary Cooling System (SACS) heat exchangers during the DBA. There are no credible failure modes introduced by these changes. All actions can be completed from the control room within a reasonable time frame with available equipment. The proposed procedural changes will not alter the original system configuration but will improve system reliability. The procedure changes are required to mitigate the effects of the DBA while meeting the UFSAR description of the SW system. The procedural changes and operator actions will enhance the system reliability to withstand an active failure and mitigate the consequences of the DBA. The changes will eliminate a single active failure that can cause a partialloss of the required SW flow path. The operator actions will ensure that SACS cooling water temperature is maintained within design limits. The minimum required components necessary to achieve and maintain cold shutdown conditions will be available. There is no postulated increase in the ofTsite does and 10CFR100 limits are not challenged by this change since all design parameters are maintained. In addition, the change will maintain the same margin of safety as currently implied )
by the TS. The assumptions used in the UFSAR chapter 15 accident analysis will not change.
Therefore, this change does not increase the probability or consequences of an accident previously described in the UFSAR and does not involve an Unreviewed Safety Question.
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Other Summary of Safety Evaluation Temporary Modifications Summary of Safety Evaluations Deficiency Reports Summary of Safety Evaluations There were no changes in these categories implemented during July 1996.
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