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| | issue date = 04/21/1995 | | | issue date = 04/21/1995 |
| | title = Informs of Review of NRC Accident Sequence Precursor Analysis Re 940407 Reactor Trip & Safety Injection at Facility.Eops Used During 940407 Event Encl | | | title = Informs of Review of NRC Accident Sequence Precursor Analysis Re 940407 Reactor Trip & Safety Injection at Facility.Eops Used During 940407 Event Encl |
| | author name = HAGAN J J | | | author name = Hagan J |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:* J. Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 211995 Vice President | | {{#Wiki_filter:* |
| -Nuclear Operations ( LR-N95064 Document Control Desk United states Nuclear Regulatory Commission Washington, DC 20555 Gentlemen: | | J. Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations A~R 211995 LR-N95064 Document Control Desk United states Nuclear Regulatory Commission Washington, DC 20555 Gentlemen: |
| REVIEW OF NRC ACCIDENT SEQUENCE PRECURSOR ANALYSIS SALEM UNIT NO. 1 DOCKET NO. 50-272 We have reviewed the Accident Sequence Precursor (ASP) Analysis relating to the April 7, 1994 reactor trip and safety injection at Salem Unit 1. While the Event Description and Additional Event Related Information sections of the ASP are accurate, we believe that the assumed value* for human error associated with realigning the auxiliary feedwater (AFW) pump suction source from the auxiliary feedwater storage tank (AFWST) *to an alternate source is overly conservative. | | REVIEW OF NRC ACCIDENT SEQUENCE PRECURSOR ANALYSIS SALEM UNIT NO. 1 DOCKET NO. 50-272 We have reviewed the Accident Sequence Precursor (ASP) Analysis relating to the April 7, 1994 reactor trip and safety injection at Salem Unit 1. While the Event Description and Additional Event Related Information sections of the ASP are accurate, we believe that the assumed value* for human error associated with realigning the auxiliary feedwater (AFW) pump suction source from the auxiliary feedwater storage tank (AFWST) *to an alternate source is overly conservative. A probability of .04 has been assigned to this input whereas the plant specific value for this event has been calculated to be 8.3E-4. We feel that the plant specific value is appropriate considering that multiple alarms and proceduralized actions would have to fail in order for the realignment not to occur. Since the assumed value for human error dominates the conditional core damage probability calculation presented in your analysis, we request that you consider the information provided below as a basis for revising the calculation. |
| A probability of .04 has been assigned to this input whereas the plant specific value for this event has been calculated to be 8.3E-4. We feel that the plant specific value is appropriate considering that multiple alarms and proceduralized actions would have to fail in order for the realignment not to occur. Since the assumed value for human error dominates the conditional core damage probability calculation presented in your analysis, we request that you consider the information provided below as a basis for revising the calculation. | | Technical Specifications require the AFWST be maintained at >90% |
| Technical Specifications require the AFWST be maintained at >90% level. A control console alarm occurs at 94% level (205,000 gallons) to indicate that the Technical Specification Limit is being approached. | | level. A control console alarm occurs at 94% level (205,000 gallons) to indicate that the Technical Specification Limit is being approached. Additional alarms occur at 43.1% level (100,000 gallons) and at 10.3% level (30,000 gallons) to alert the operator to an impending low level condition. Alarm response procedure Sl.OP-AR.ZZ-0012(Q) directs the operator to take appropriate action to initiate refill of the tank or to realign to an alternate source if the AFWST tank has become inoperable. |
| Additional alarms occur at 43.1% level (100,000 gallons) and at 10.3% level (30,000 gallons) to alert the operator to an impending low level condition. | | ( 9505020319 6~865~72 |
| Alarm response procedure Sl.OP-AR.ZZ-0012(Q) directs the operator to take appropriate action to initiate refill of the tank or to realign to an alternate source if the AFWST tank has become inoperable. | | ~DR ADOCK . PDR |
| 9505020319 ADOCK . PDR rt, ' | | ~oo( |
| 1-... APR 211995 ' . Docufuent Control Desk 2 LR-N95064 Emergency Operating Procedures (EOP) used during the April 7 event also contain provisions to ensure that the alternate suction alignment is accomplished in a timely manner. Procedures 1-EOP-TRIP-1,2
| | rt, ' |
| & 3 all contain Continuous Action Summary (CAS) statements directing the realignment of the AFW pump suction to an alternate source if AFWST level decreases below 14%. The CAS's are monitored by the operator and the Shift Technical Advisor throughout an event and appropriate actions taken when directed.
| |
| The above referenced are provided as Attachment 1, and are submitted in accordance with the guidelines provided in your request for comments.
| |
| If there are any questions regarding the information contained herein, please feel free to contact us. Sincerely, Attachment 95-4933
| |
| .. t L Docdment Control Desk 3 LR-N95064 c Mr. T. T. Martin, Administrator
| |
| -Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager -Salem u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. c. Marschall (S09) USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
| |
| *
| |
| * ATTACHMENT 1 The following procedures are provided for reference purposes; S1.0P-AR.ZZ-0012(Q)
| |
| Rev. 6 (pages 78-80) 1-EOP-TRIP-1 Rev. 11 1-EOP-TRIP-2 Rev. 12 1-EOP-TRIP-3 Rev. 10 e S 1.0P-AR.ZZ-0012(Q)
| |
| SYSTEM AUXILIARY FEED SYSTEM Aux Feedwater Storage Tank -----------------------------------,_ BEZEL Alarms & Display DEVICES: lLD-3349 SETPOINT:
| |
| 94% (205,000 gals) 1.0 CAUSE(S):
| |
| AFWST LEVEL APPROACIIlNG TECH SPEC 1.1 Level in AFWST approaching Technical Specification minimum 2.0 AUTOMATIC ACTIONS: 2.1 None 3.0 OPERATOR ACTIONS: 3.1 MONITOR AFWST level on Console indications.
| |
| 3.2 OPEN 1DR6, AFW TANK MAKEUP VALVE, as necessary to maintain level > 90% (T/S minimum) and CONTINUOUSLY MONITOR AFWST level to preclude overflow condition.
| |
|
| |
|
| ===3.3 ATTEMPT=== | | 1- |
| to detennine cause of level decrease. | | ... APR 211995 |
| A. IF cause cannot be detennined, THEN PERFORM following: | | ' Docufuent Control Desk LR-N95064 2 |
| : 1. SEND an Operator to locate any leakage. 2. INITIATE Work Request to detennine and correct cause of low level. Page 1of1 4-12 | | Emergency Operating Procedures (EOP) used during the April 7 event also contain provisions to ensure that the alternate suction alignment is accomplished in a timely manner. Procedures 1-EOP-TRIP-1,2 & 3 all contain Continuous Action Summary (CAS) statements directing the realignment of the AFW pump suction to an alternate source if AFWST level decreases below 14%. The CAS's are monitored by the operator and the Shift Technical Advisor throughout an event and appropriate actions taken when directed. |
| | The above referenced proc~dures are provided as Attachment 1, and are submitted in accordance with the guidelines provided in your request for comments. If there are any questions regarding the information contained herein, please feel free to contact us. |
| | Sincerely, Attachment 95-4933 |
| | |
| | t Docdment Control Desk 3 LR-N95064 c Mr. T. T. Martin, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager - Salem |
| | : u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. c. Marschall (S09) |
| | USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 L |
| | |
| | ATTACHMENT 1 The following procedures are provided for reference purposes; S1.0P-AR.ZZ-0012(Q) Rev. 6 (pages 78-80) 1-EOP-TRIP-1 Rev. 11 1-EOP-TRIP-2 Rev. 12 1-EOP-TRIP-3 Rev. 10 |
| | |
| | e S 1.0P-AR.ZZ-0012(Q) |
| | SYSTEM AUXILIARY FEED SYSTEM Aux Feedwater Storage Tank AFWST |
| | -- - -- LEVEL APPROACIIlNG TECH SPEC BEZEL Alarms & Display DEVICES: lLD-3349 SETPOINT: 94% (205,000 gals) |
| | |
| | ==1.0 CAUSE(S)== |
| | 1.1 Level in AFWST approaching Technical Specification minimum 2.0 AUTOMATIC ACTIONS: |
| | 2.1 None 3.0 OPERATOR ACTIONS: |
| | 3.1 MONITOR AFWST level on Console indications. |
| | 3.2 OPEN 1DR6, AFW TANK MAKEUP VALVE, as necessary to maintain level |
| | > 90% (T/S minimum) and CONTINUOUSLY MONITOR AFWST level to preclude overflow condition. |
| | 3.3 ATTEMPT to detennine cause of level decrease. |
| | A. IF cause cannot be detennined, THEN PERFORM following: |
| | : 1. SEND an Operator to locate any leakage. |
| | : 2. INITIATE Work Request to detennine and correct cause of low level. |
| | Page 1of1 4-12 |
|
| |
|
| ==References:== | | ==References:== |
| | Dwg. 248884, 205236, 611444 Salem 1 Page 78 of 127 Rev. 6 |
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| |
|
| Dwg. 248884, 205236, 611444 Salem 1 Page 78 of 127 Rev. 6
| | S 1.0P-AR.ZZ-0012(Q) |
| ** S 1.0P-AR.ZZ-0012(Q)
| | SYSTEM AUXIUARY FEED SYSTEM Aux Feedwater Storage Tank 11111111m~1 AFWST CH C (A) |
| SYSTEM AUXIUARY FEED SYSTEM Aux Feedwater Storage Tank BEZEL Alarms & Display Channel C Channel A DEVICES: lLD-2701 lLD-2955 SETPOINT: | | LEVEL LO BEZEL Alarms & Display Channel C Channel A DEVICES: lLD-2701 lLD-2955 SETPOINT: 43.1 % (100,000 gals) |
| 43.1 % (100,000 gals) 1.0 CAUSE(S): | |
| 1.1 I.ow level in AFWST 2.0 AtITOMATIC ACTIONS: 2.1 None 3.0 OPERATOR ACTIONS: 3.1 MONITOR AFWST level on Console indications.
| |
| AFWST CH C (A) LEVEL LO 3.2 OPEN 1DR6, AFW TANK MAKEUP VALVE, as necessary to maintain level > 90% (TIS minimum) and CONTINUOUSLY MONITOR AFWST level to preclude overflow condition.
| |
| : 3. 3 IE level cannot be restored, THEN INITIATE efforts to transfer suction of affected pump(s) to an alternate source of water IAW Sl.OP-SO.AF-OOOl(Q), Auxiliary Feedwater System Operation.
| |
|
| |
|
| ===3.4 ATIEMPT=== | | ==1.0 CAUSE(S)== |
| to detennine cause of level decrease. | | 1.1 I.ow level in AFWST 2.0 AtITOMATIC ACTIONS: |
| A. IF cause cannot be detennioed, THEN PERFORM following: | | 2.1 None 3.0 OPERATOR ACTIONS: |
| : 1. SEND an Operator to locate any leakage. 2. INITIATE Work Request to determine and correct cause of low level. Page 1of1 4-12 | | 3.1 MONITOR AFWST level on Console indications. |
| | 3.2 OPEN 1DR6, AFW TANK MAKEUP VALVE, as necessary to maintain level |
| | > 90% (TIS minimum) and CONTINUOUSLY MONITOR AFWST level to preclude overflow condition. |
| | : 3. 3 IE level cannot be restored, THEN INITIATE efforts to transfer suction of affected pump(s) to an alternate source of water IAW Sl.OP-SO.AF-OOOl(Q), Auxiliary Feedwater System Operation. |
| | 3.4 ATIEMPT to detennine cause of level decrease. |
| | A. IF cause cannot be detennioed, THEN PERFORM following: |
| | : 1. SEND an Operator to locate any leakage. |
| | : 2. INITIATE Work Request to determine and correct cause of low level. |
| | Page 1of1 4-12 |
|
| |
|
| ==References:== | | ==References:== |
| | Dwg. 203313, 248884, 205236, 611441, 611443 Salem 1 Page 79of127 Rev. 6 |
|
| |
|
| Dwg. 203313, 248884, 205236, 611441, 611443 Salem 1 Page 79of127 Rev. 6 S 1.0P-AR.ZZ-0012(Q)
| | S 1.0P-AR.ZZ-0012(Q) |
| SY SIEM AUXIUARY FEED SYSTEM Aux Feedwater Storage Tanlc 11111111mm 1 BEZEL Alanns & Display DEVICES: Channel C lLD-2671 Channel A ILD-3601 SETPOINT:
| | SYSIEM AUXIUARY FEED SYSTEM Aux Feedwater Storage Tanlc AFWST CH C (A) 11111111mm LEVEL LO-W 1 |
| 10.3 % (30,000 gals) 1.0 CAUSE(S): | | BEZEL Alanns & Display Channel C Channel A DEVICES: lLD-2671 ILD-3601 SETPOINT: 10.3 % (30,000 gals) |
| 1.1 Low-Low level in AFWST 2.0 AUTOMATIC ACTIONS: 2.1 None 3.0 OPERATOR ACTIONS: 3.1 MONITOR AFWST level on Console indications.
| |
| AFWST CH C (A) LEVEL LO-W 3.2 TRANSFER.
| |
| suction of any running AFW pumps to an alternate source of water IAW Sl.OP-SO.AF-OOOl(Q), Auxiliary Feedwater System Operation.
| |
| 3.3 OPEN 1DR6, AFW TANK MAKEUP VALVE, as necessary to maintain level > 90% (f/S minimum) and CONTINUOUSLY MONITOR AFWST level to preclude overflow condition.
| |
|
| |
|
| ===3.4 ATTEMPT=== | | ==1.0 CAUSE(S)== |
| to determine cause of level decrease. | | 1.1 Low-Low level in AFWST 2.0 AUTOMATIC ACTIONS: |
| A. D: cause cannot be detennined, THEN: 1. SEND an Operator to locate any leakage. 2. INITIATE Work Request to determine and correct cause of low level. Page 1 of 1 4-12 | | 2.1 None 3.0 OPERATOR ACTIONS: |
| | 3.1 MONITOR AFWST level on Console indications. |
| | 3.2 TRANSFER. suction of any running AFW pumps to an alternate source of water IAW Sl.OP-SO.AF-OOOl(Q), Auxiliary Feedwater System Operation. |
| | 3.3 OPEN 1DR6, AFW TANK MAKEUP VALVE, as necessary to maintain level |
| | > 90% (f/S minimum) and CONTINUOUSLY MONITOR AFWST level to preclude overflow condition. |
| | 3.4 ATTEMPT to determine cause of level decrease. |
| | A. D: cause cannot be detennined, THEN: |
| | : 1. SEND an Operator to locate any leakage. |
| | : 2. INITIATE Work Request to determine and correct cause of low level. |
| | Page 1 of 1 4-12 |
|
| |
|
| ==References:== | | ==References:== |
| | | Dwg. 203313, 248884, 205236, 611442, 611445 Salem 1 Page 80 of 127 Rev. 6}} |
| Dwg. 203313, 248884, 205236, 611442, 611445 Salem 1 Page 80 of 127 Rev. 6}} | |
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Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999
ML18107A5221999-09-0808 September 1999
Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations
ML18107A5061999-08-26026 August 1999
Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151
ML18107A5181999-08-26026 August 1999
Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided
ML18107A4981999-08-26026 August 1999
Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues
ML18107A5051999-08-24024 August 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves
ML18107A4921999-08-23023 August 1999
Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02
ML18107A4911999-08-20020 August 1999
Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars
ML18107A4831999-08-18018 August 1999
Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1
ML18107A4801999-08-13013 August 1999
Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed
ML18107A4751999-08-0505 August 1999
Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630
ML20210M7571999-08-0404 August 1999
Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response
ML18107A4431999-07-0606 July 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments
ML18107A4181999-06-30030 June 1999
Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl
ML18107A4131999-06-25025 June 1999
Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC
ML18107A4061999-06-21021 June 1999
Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed
ML18107A3691999-06-11011 June 1999
Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours)
ML18107A3641999-06-0404 June 1999
Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1
ML18107A3561999-06-0303 June 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments
ML18107A3611999-05-27027 May 1999
Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05
ML18107A3301999-05-24024 May 1999
Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves
ML18107A3291999-05-20020 May 1999
Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6)
ML18107A3031999-05-18018 May 1999
Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments
ML18107A2891999-05-13013 May 1999
Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness
ML18107A2951999-05-12012 May 1999
Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO
ML18107A2861999-05-11011 May 1999
Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE
ML18107A2481999-04-29029 April 1999
Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998
ML18107A2511999-04-27027 April 1999
Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses
ML18107A2371999-04-26026 April 1999
Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal
ML18107A2631999-04-26026 April 1999
Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements
ML18107A2411999-04-22022 April 1999
Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics
ML18107A1841999-04-14014 April 1999
Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl
ML18107A1981999-04-12012 April 1999
Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202
ML18107A1691999-04-12012 April 1999
Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld
ML20205K4541999-04-0808 April 1999
Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept
ML18106B1491999-04-0505 April 1999
Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined
ML20205F8981999-03-31031 March 1999
Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1)
ML18106B1431999-03-31031 March 1999
Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75
ML18107A2201999-03-30030 March 1999
Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek
1999-09-08
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Text
J. Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations A~R 211995 LR-N95064 Document Control Desk United states Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:
REVIEW OF NRC ACCIDENT SEQUENCE PRECURSOR ANALYSIS SALEM UNIT NO. 1 DOCKET NO. 50-272 We have reviewed the Accident Sequence Precursor (ASP) Analysis relating to the April 7, 1994 reactor trip and safety injection at Salem Unit 1. While the Event Description and Additional Event Related Information sections of the ASP are accurate, we believe that the assumed value* for human error associated with realigning the auxiliary feedwater (AFW) pump suction source from the auxiliary feedwater storage tank (AFWST) *to an alternate source is overly conservative. A probability of .04 has been assigned to this input whereas the plant specific value for this event has been calculated to be 8.3E-4. We feel that the plant specific value is appropriate considering that multiple alarms and proceduralized actions would have to fail in order for the realignment not to occur. Since the assumed value for human error dominates the conditional core damage probability calculation presented in your analysis, we request that you consider the information provided below as a basis for revising the calculation.
Technical Specifications require the AFWST be maintained at >90%
level. A control console alarm occurs at 94% level (205,000 gallons) to indicate that the Technical Specification Limit is being approached. Additional alarms occur at 43.1% level (100,000 gallons) and at 10.3% level (30,000 gallons) to alert the operator to an impending low level condition. Alarm response procedure Sl.OP-AR.ZZ-0012(Q) directs the operator to take appropriate action to initiate refill of the tank or to realign to an alternate source if the AFWST tank has become inoperable.
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' Docufuent Control Desk LR-N95064 2
Emergency Operating Procedures (EOP) used during the April 7 event also contain provisions to ensure that the alternate suction alignment is accomplished in a timely manner. Procedures 1-EOP-TRIP-1,2 & 3 all contain Continuous Action Summary (CAS) statements directing the realignment of the AFW pump suction to an alternate source if AFWST level decreases below 14%. The CAS's are monitored by the operator and the Shift Technical Advisor throughout an event and appropriate actions taken when directed.
The above referenced proc~dures are provided as Attachment 1, and are submitted in accordance with the guidelines provided in your request for comments. If there are any questions regarding the information contained herein, please feel free to contact us.
Sincerely, Attachment 95-4933
t Docdment Control Desk 3 LR-N95064 c Mr. T. T. Martin, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager - Salem
- u. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. c. Marschall (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 L
ATTACHMENT 1 The following procedures are provided for reference purposes; S1.0P-AR.ZZ-0012(Q) Rev. 6 (pages 78-80) 1-EOP-TRIP-1 Rev. 11 1-EOP-TRIP-2 Rev. 12 1-EOP-TRIP-3 Rev. 10
e S 1.0P-AR.ZZ-0012(Q)
SYSTEM AUXILIARY FEED SYSTEM Aux Feedwater Storage Tank AFWST
-- - -- LEVEL APPROACIIlNG TECH SPEC BEZEL Alarms & Display DEVICES: lLD-3349 SETPOINT: 94% (205,000 gals)
1.0 CAUSE(S)
1.1 Level in AFWST approaching Technical Specification minimum 2.0 AUTOMATIC ACTIONS:
2.1 None 3.0 OPERATOR ACTIONS:
3.1 MONITOR AFWST level on Console indications.
3.2 OPEN 1DR6, AFW TANK MAKEUP VALVE, as necessary to maintain level
> 90% (T/S minimum) and CONTINUOUSLY MONITOR AFWST level to preclude overflow condition.
3.3 ATTEMPT to detennine cause of level decrease.
A. IF cause cannot be detennined, THEN PERFORM following:
- 1. SEND an Operator to locate any leakage.
- 2. INITIATE Work Request to detennine and correct cause of low level.
Page 1of1 4-12
References:
Dwg. 248884, 205236, 611444 Salem 1 Page 78 of 127 Rev. 6
S 1.0P-AR.ZZ-0012(Q)
SYSTEM AUXIUARY FEED SYSTEM Aux Feedwater Storage Tank 11111111m~1 AFWST CH C (A)
LEVEL LO BEZEL Alarms & Display Channel C Channel A DEVICES: lLD-2701 lLD-2955 SETPOINT: 43.1 % (100,000 gals)
1.0 CAUSE(S)
1.1 I.ow level in AFWST 2.0 AtITOMATIC ACTIONS:
2.1 None 3.0 OPERATOR ACTIONS:
3.1 MONITOR AFWST level on Console indications.
3.2 OPEN 1DR6, AFW TANK MAKEUP VALVE, as necessary to maintain level
> 90% (TIS minimum) and CONTINUOUSLY MONITOR AFWST level to preclude overflow condition.
- 3. 3 IE level cannot be restored, THEN INITIATE efforts to transfer suction of affected pump(s) to an alternate source of water IAW Sl.OP-SO.AF-OOOl(Q), Auxiliary Feedwater System Operation.
3.4 ATIEMPT to detennine cause of level decrease.
A. IF cause cannot be detennioed, THEN PERFORM following:
- 1. SEND an Operator to locate any leakage.
- 2. INITIATE Work Request to determine and correct cause of low level.
Page 1of1 4-12
References:
Dwg. 203313, 248884, 205236, 611441, 611443 Salem 1 Page 79of127 Rev. 6
S 1.0P-AR.ZZ-0012(Q)
SYSIEM AUXIUARY FEED SYSTEM Aux Feedwater Storage Tanlc AFWST CH C (A) 11111111mm LEVEL LO-W 1
BEZEL Alanns & Display Channel C Channel A DEVICES: lLD-2671 ILD-3601 SETPOINT: 10.3 % (30,000 gals)
1.0 CAUSE(S)
1.1 Low-Low level in AFWST 2.0 AUTOMATIC ACTIONS:
2.1 None 3.0 OPERATOR ACTIONS:
3.1 MONITOR AFWST level on Console indications.
3.2 TRANSFER. suction of any running AFW pumps to an alternate source of water IAW Sl.OP-SO.AF-OOOl(Q), Auxiliary Feedwater System Operation.
3.3 OPEN 1DR6, AFW TANK MAKEUP VALVE, as necessary to maintain level
> 90% (f/S minimum) and CONTINUOUSLY MONITOR AFWST level to preclude overflow condition.
3.4 ATTEMPT to determine cause of level decrease.
A. D: cause cannot be detennined, THEN:
- 1. SEND an Operator to locate any leakage.
- 2. INITIATE Work Request to determine and correct cause of low level.
Page 1 of 1 4-12
References:
Dwg. 203313, 248884, 205236, 611442, 611445 Salem 1 Page 80 of 127 Rev. 6
