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| | issue date = 06/21/1999 | | | issue date = 06/21/1999 |
| | title = Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed | | | title = Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed |
| | author name = STORZ L F | | | author name = Storz L |
| | 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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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. 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 ML18107A5231999-09-0808 September 1999 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 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 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 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 ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection 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 ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection 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 ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 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 ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 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 ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection 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 ML18107A3371999-05-21021 May 1999 Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622 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 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 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 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5231999-09-0808 September 1999 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 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 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 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 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. 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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
[Table view] |
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Louis F. Storz Public Service Electric and Gas Company Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President
-Nuclear Operations LR-N990273 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SUPPLEMENTAL INFORMATION FOR REQUEST FOR LICENSE AMENDMENT AUXILIARY BUILDING VENTILATION SALEM GENERA TING STATION UNITS 1.AND 2 JUN21199a*
FACILITY OPERA TING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 By letter dated February 17, 1999, Public Service Electric and Gas Company (PSE&G) provided the Nuclear Regulatory Commission (NRC) with the additional information relative to the PSE&G propos_ed amendment to modify Technical
- Specification 3/4 7.7 "Auxiliary Building Exhaust Air Filtration System." (TAC Nos. M99875 and M99876). During PSE&G's review of the proposed changes relative fo procedural changes, PSE&G noted a discrepancy in the submittal relative to testing requirements.
Specifically, PSE&G agreed to test the charcoal adsorber to a removal efficiency of;;:: 90% of methyl iodine at 30 6 C and 95% R.H. This acceptance criterion is based on ASTM 03803 Revision 1989, for a standard charcoal bed of 2 inches in depth. The Salem station Auxiliary Building Exhaust Air Filtration System charcoal train is a one-inch depth bed. Consequently, an acceptance criterion of;;:: 90% of methyl .1 iodine at 30 °C and 95% R.H is not appropriate.
Subsequently, to this finding, PSE&G notified the Salem NRC Project Manager that a new acceptance criterion had to be determined for the Salem configuration.
PSE&G determined that an acceptance criterion of;;:: 80% for methyl iodine is appropriate for a 1-inch charcoal bed. This acceptance criterion allows for a (\ 0 0 \ reasonable degradation due to use and is consistent with the acceptance criterion
\, of ASTM 03803. The Salem off-site and control room dose calculation was revised using the 80% value for methyl iodine and has been shown to yield acceptable results. @, Printed on Recycled Paper -i
<' Document Control Desk LR-N990273 The TACT5 computer code in the HABIT computer code package was used to determine off-site doses rather than using Stone and Webster Engineering Corporation's proprietary PERC2 computer code. Additionally, the CONHAB computer code in the HABIT computer code package and the MicroShield Version 4.21 computer code were used to determine control room doses rather than using Stone and Webster Engineering Corporation's proprietary PERC2 computer code and the QAD-P5A computer program. The re-analysis incorporates a number of parameter value changes. These are: a) Ninety-one percent of all radioactive iodine released is assumed to be in the form of elemental iodine, 5 percent in the form of particulate iodine, and 4 percent in the form of organic iodides. In our previous analysis, the radioactive iodine released before containment isolation and the radioactive iodine released as a result of Engineering Safety Feature (ESF) leakage outside containment was assumed to be entirely in the form of elemental iodine. This change was made to simplify the analysis and use more appropriate fractions for the ESF leakage contribution.
b) The ESF leakage rate outside containment was assumed to be 7600 cc/hr rather than 7680 cc/hr to be more consistent with design basis documentation and station leakage control procedures.
c) The Auxiliary Building exhaust air filtration system HEPA filter particulate removal efficiency was assumed to be 95 percent to be consistent with the radioactive iodine species assumed. Previously the Auxiliary Building exhaust air filtration system HEPA filters were not credited in the analysis because the radioactive iodine released as a result of ESF leakage outside containment was assumed to be entirely in the form of elemental iodine. d) It was assumed that all ESF leakage outside containment that becomes airborne passes through HEPA filters. e) The Auxiliary Building exhaust air filtration system charcoal bank organic iodide removal efficiency was assumed to be 80 percent after charcoal bank alignment to be consistent with the radioactive iodine species assumed. Previously the Auxiliary Building exhaust air filtration system organic iodide removal was not credited in the analysis because the radioactive iodine released as a result of ESF leakage outside containment was assumed to be entirely in the form of elemental iodine. 95-4933 JUN211999 Document Control Desk LR-N990273 f) The control room envelope was assumed to be fully pressurized within one minute rather than 48 seconds in order to simplify the analysis model. Attachment I contains the revised limiting condition for operation submitted in our February 17, 1999 letter (Ref: LR-N990085).
Additionally, the word "efficiency" is also added following the word "removal" to clarify the sentence, and the word ASTM replaces the word ANSI. PSE&G has reviewed the no safety hazards evaluation submitted in support of our original submittal (LR-N97488), and determined that it remains valid. Should there be any additional questions or comments on this transmittal, please do not hesitate to contact us. Attachment (1) Affidavit Sincerely, C Mr. H.J. Miller, Administrator
-Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager -Salem U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockviile Pike Mail Stop 14E21 Rockville, MD 20852 Mr. S. Morris USNRC Senior Resident Inspector (X24) Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 95-4933 STATE OF NEW JERSEY) ) SS. COUNTY OF SALEM ) REF: LR-N990273 LCR S95-44 L. F. Storz, being duly sworn according to law deposes and says: I am Senior Vice President
-Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Salem Generating Station, Units 1 and 2, are true to the best of my knowledge, information and belief. Subscribed and Sworn to before me day of lh;..;e,, , 1999 .Nota1yPublic of New Jersey "'** -' . DELORIS 0. HADDEN Notary Public of New Jerlar My Commission Expires . M C . . . 03-29-2000 y omm1ss1on expires on _____________
_ I I !
LR-N990273 ATTACHMENT I SUPPLEMENTAL INFORMATION FOR REQUEST FOR LICENSE AMENDMENT AUXILIARY BUILDING VENTILATION SALEM GENERATING STATION UNITS 1AND2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 The Insert material from Request for License Amendment originally submitted in our February 17, 1999 letter (Ref: N990085) is shown below with currently proposed changes. The proposed changes are shown in Bold for emphasis.
Insert A (LCO UNIT 1) Three Auxiliary Building exhaust air HEPA filter trains, one carbon adsorber bank, two supply fans, and three exhaust fans, shall be OPERABLE L}. Insert 8 (ACTION) a. With one HEPA filter train inoperable, restore the inoperable HEPA filter train to OPERABLE status within 7 days or be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. b. With no HEPA train associated with the one Carbon Adsorber operable, restore at least one associated HEPA train to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STAND-BY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. c. With the carbon adsorber inoperable, restore the carbon adsorber to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. d. With one supply fan or one exhaust fan inoperable, restore the fan to OPERABLE status within 14 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. e. With less than two exhaust fans operable restore one exhaust fan to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. f. With no supply fans operable, be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. (*)One of the Supply Fans may be considered OPERABLE with its start circuit administratively controlled (removed from service) to prevent more than one supply -
LR-N990273 ATTACHMENT I SUPPLEMENTAL INFORMATION FOR REQUEST FOR LICENSE AMENDMENT AUXILIARY BUILDING VENTILATION SALEM GENERATING STATION UNITS 1AND2 FACILITY OPERA TING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 fan from operating at any time. (SURVEILLANCE REQUIREMENTS)
Insert C (UNIT 1 TS 4.7.7.1) The Auxiliary Building Exhaust air filtration system shall be demonstrated OPERABLE:
- a. At least once each 31 days by aligning to the ECCS flow path and initiating flow for at least 15 minutes (for each train) through: 1. filter train 11 and carbon adsorber train 14, then 2. filter train 12 and carbon adsorber train 14 b. At least once each 18 months, or (1) following painting, fire or chemical release in any ventilation zone communicating with the system, or (2) any partial or complete replacement of the HEPA or carbon filters, by: 1. Verifying that, with the ECCS duct flow path and HEPA train 11 aligned to carbon adsorber train 14 and operating at a flow rate of 21,400 CFM +/-10%, the total bypass flow is less than or equal to 1 % when tested by injecting halogenated hydrocarbon refrigerant.
- 2. Verifying that, with the ECCS duct flow path and HEPA train 12 aligned to carbon adsorber train 14 and operating at a flow rate of 21,400 CFM +/-10%, the total bypass flow is less than or equal to 1 % when tested by injecting halogenated hydrocarbon refrigerant.
- 3. Verifying that, in-place leak testing of the carbon adsorber train 14 removes 2::99% of a halogenated hydrocarbon refrigerant test gas when tested at 21,400 CFM +/-10% in accordance with Regulatory Guide 1.52 Rev 2, 1978, Section C.5.d. 4. Verifying that, in-place leak testing of HEPA filter banks in LR-N990273 ATTACHMENT I SUPPLEMENTAL INFORMATION FOR REQUEST FOR LICENSE AMENDMENT AUXILIARY BUILDING VENTILATION SALEM GENERATING STATION UNITS 1AND2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 trains 11, 12, 13 will remove 99% of DOP when tested at their rated design flow capacity +/-10% for each housing in
- accordance with Regulatory Guide 1.52 Rev 2, 1978, Section C.5.c. 5. Verifying within 31 days after removal that laboratory analysis of a representative carbon sample demonstrates a removal efficiency of methyl iodine when tested at 30 degree C and 95% RH in accordance with ASTM 03803 Revision 1989. 6. Verifying that flow rate through the carbon adsorber does not exceed 21,400 CFM +/- 10% when either HEPA+ carbon adsorber combination is aligned to the ECCS areas. 7.a. Verifying the total pressure drop across HEPA train 11 and carbon adsorber train 14 is Water Gauge when tested at 21,400 CFM +/-10%. 7.b. Verifying the total pressure drop across HEPA train 12 and carbon adsorber train 14 is Water Gauge when tested at 21,400 CFM +/-10%. .
' ' LR-N990273 ATTACHMENT I SUPPLEMENTAL INFORMATION FOR REQUEST FOR LICENSE AMENDMENT AUXILIARY BUILDING VENTILATION SALEM GENERATING STATION UNITS 1AND2 FACILITY OPERA TING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Insert D (UNIT 1 4.7.7.1) c. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation verify that within 31 days after removal that laboratory analysis of a representative carbon sample demonstrates a removal efficiency of methyl iodine when tested at 30 degree C and 95 % RITTn accordance with ASTM 03803 Revision 1989. d. After maintenance affecting the flow distribution, verify that the airflow distribution of the system is acceptable when tested in accordance with Regulatory Guide 1.52, Revision 2, 1978 Section C.5.b. e. After any structural maintenance on the HEPA or carbon adsorber unit mounting frames or housing, perform tests as required by surveillance 4.7.7.1.b.1 through 4.7.7.1.b.4.
- f. After operation of Auxiliary Building normal flow path through the carbon adsorber, prior to mode 4 entry, verify the carbon adsorber will remove of a halogenated hydrocarbon refrigerant test gas when in-place leak tested at a flow rate of 21,400 CFM +/-10%. g. After operation of containment purge exhaust flow path through the carbon adsorber, prior to mode 4 entry, verify the carbon adsorbers will remove of a halogenated hydrocarbon refrigerant test gas when in-place leak tested at a flow rate of 21,400 CFM +/-10%. The same changes described above are applicable to the Salem 2 Technical Specifications.
Insert J ( UNIT 1 & 2 BASES) No changes are required from the original insert.