LR-N990289, 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 & Discussion with NRC
ML18107A412
ML20209B675
LR-N990251, Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl
ML20196J630
ML18107A443
ML18107A425
ML18107A431
ML18107A438
ML18107A436
ML18107A453
ML18107A471
ML18107A470
ML20210M757
ML18107A475
ML18107A477
LR-N990140, Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed
LR-N990375, Submits Licensee Comments on NRC Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1
ML18107A486
LR-N990389, 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
LR-N990363, 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
ML18107A505
ML18107A500
LR-N990385, 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
ML18107A506
LR-N990396, Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided
LR-N990392, 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
LR-N990406, 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
ML18107A535
LR-N990405, 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
LR-N000420, Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2
ML20212B363
ML18107A537
ML18107A542
NTD-99-302, Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)
ML18107A546
ML18107A540
ML18107A547
ML18107A559
ML18107A552
ML18107A550
LR-N990409, Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests
ML18107A551
ML18107A553
LR-N990450, 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
LR-N990170, Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202
ML18107A184
ML18107A241
LR-N990197, 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 to Nrc.Encl Supersedes 990412 Submittal
LR-N990196, Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements
LR-N990200, 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
ML18107A248
LR-N990227, Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE
LR-N990238, 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
ML18107A289
ML18107A303
LR-N990249, 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)
LR-N990254, 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
LR-N990240, Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05
ML18107A356
LR-N990272, Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1
LR-N99-0283, 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)
LR-N990273, Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed
LR-N990289, 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 & Discussion with NRC
LR-N990251, Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl
ML18107A443
ML20210M757
ML18107A475
LR-N990140, Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed
LR-N990375, Submits Licensee Comments on NRC Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1
LR-N990389, 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
LR-N990363, 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
ML18107A505
LR-N990396, Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided
ML18107A506
LR-N990385, 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
LR-N990406, 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
LR-N990392, 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
ML18107A535
LR-N000420, Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2
LR-N990405, 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
ML20212B363
NTD-99-302, Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)
ML18107A550
ML18107A559
ML18107A552
LR-N990409, Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests
ML18107A553
LR-N990450, 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
Public Service Electric and Gas Company E. C. Simpson Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700.
Senior Vice President - Nuclear Engineering U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk IAY181999 LR-N99092 1998
SUMMARY
OF REVISED REGULATORY COMMITMENTS SALEM GENERATING STATION SALEM UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Gentlemen:
This correspondence is being transmitted in accordance with the Nuclear Energy Institute (NEI) process for managing NRC commitments and associated NRC notification. It provides a summary of changes to NRC commitments that have been made but not reported by other means. The following information is provided regarding each of the changed commitments and their source documents.
LER 272/97-013-00, "Failure To Meet Technical Specification 3.8.1.1, Action 8" This LER reported the inoperability of an Emergency Diesel Generator (EOG) because of the failure of plant personnel to remove test equipment from the EOG following the completion of a Technical Specification surveillance. One corrective action of this LER to prevent recurrence was to develop generic guidance to provide appropriate direction for the installation of temporary test instrumentation into operable plant equipment.
This action was to be completed by January 30, 1998. Because of other priorities required to support the Salem Unit 1 restart, completion of this corrective action was extended until March 31, 1998.
LER 311/97-008-00, "Failure To Enter Action Statement For Having Both Radiation Monitors In The Same Control Room Air Intake Duct Inoperable" This LER reported the failure of Operations personnel to recognize the necessity for entry into a Technical Specification action statement because.of inoperable radiation monitors. In order to avoid similar human errors in the future, a corrective action commitment to this LER was made to revise the nomenclature of the Control Room Air
Intake Duct Radiation Monitor channels to improve the human factors of the system.
This commitment was originally to be met by 12/01/97. As reported in the Salem 1997 summary of revised regulatory commitments, this commitment was extended to 3/31/98 due to work prioritization. Upon further evaluation, Operations and Engineering personnel determined that a new labeling scheme would not reduce the complexity of the indications, and that the existing nomenclature and channel designation are correct and consistent with the system configuration.
To prevent recurrence of Operations personnel failing to recognize the necessity for entry in Technical Specification action statements because of inoperable radiation monitors, the Operations department implemented several improvements to prevent recurrence. These improvements included enhancement of procedures and more effective training to make operators more familiar with the system.
Notice Of Violation 272/93-23-02, Operability Of Emergency Diesel Generators With An Air Start System Isolated In response to Notice Of Violation 272/93-23-02, PSE&G committed that when a train of EOG starting air motors is removed from service, the EOG will be tested to ensure that the remaining set of starting air motors is operable. This commitment has been revised to test the EOG starting air motors in accordance with the In-service Testing (IST)
Program 92-day test. When the original commitment was made, the single train air start test was performed once every refueling outage. In 1997, during an upgrade of the IST Program, a 92-day test of the solenoid valves to the starting air motors was added. This test demonstrates the operability of each starting air train. Since the frequency of this test is 92 days, there is reasonable assurance that the diesel will start on each train regardless of which train is isolated. Therefore, testing of a starting air train because the other train is to be removed from service will no longer be performed.
Should there be any questions please contact us.
/rbk C
Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046
Document Control Desk
. LR-N,99092 3
Mr. Patrick Milano, Licensing Project Manager - Salem U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08B1 Rockville, MD 20852 Mr. Scott Morris - Salem (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625