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
SALEM UNIT 2 CYCLE 11 STARTUP REPORT SALEM GENERATING STATION -UNIT 2 FACILITY OPERATING LICENSE DPR-75 DOCKET NO. 50-311 Public Service Electric & Gas (PSE&G) Company hereby submits a summary report of plant startup and power ascension testing for Salem Unit 2 Cycle 11 in accordance with the requirements of Technical Specification 6.9.1.1. The report is required since fuel of a new design was installed for Cycle 11. A description of the fuel design changes and the summary of testing are included in Attachment 1.
ShouJd you have any questions regarding this submittal, please contact Paul Duke at (856) 339-1466.
LR-N99441 C Mr. H. 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 Mail Stop 881 11555 Rockville Pike Rockville, MD 20852 USNRC Senior Resident Inspector - Salem (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. 0. Box415 Trenton, NJ 08625 OCT 8
1999
ATTACHMENT 1 SALEM UNIT 2CYCLE11 STARTUP REPORT Salem Unit 2 began its eleventh cycle of operation on May 26, 1999 and completes operation on October 6, 2000. The burnup at the end of Cycle 11 is predicted fo be 18600 MWD/MTU. The Cycle 11 reload included one region of fresh Westinghouse RFA (Robust Fuel Assembly) fuel. This consisted of two sub regions: 44 Region 13A assemblies enriched to 4.006 w/o U235 and 28 Region 138 assemblies enriched to 4.407 w/o U235* The cycle 11 reload core utilizes 320 fresh discrete PYREX burnable absorber rods and 7392 1.25X (1.9625 mg/inch B-10) IFBA (Integral Fuel-Burnable Absorber) rods. Cycle 11 represents the first Salem reload utilizing IFM (Intermediate Flow Mixer) grids, the 1.25x IFBA loading, annular fuel pellets at the top and bottom 6'.'
of the Region 13 RFA fuel, and a protective bottom grid (a debris mitigation feature).
Salem Unit 2 Cycle 11 reload core design involved the installation of a new fuel type that had a different design than any previous Salem cycle. While various startup tests were performed, the reload core design, in particular, was verified during the startup physics testing program.
Control rod bank worth measurements via Dynamic Rod Worth Measurement (DRWM)
3.
Temperature coefficient measurements
4.
Power distribution measurements usirig the incore flux mapping system Salem Unit 2 Cycle 11 is the first cycle of implementation at Salem for the Dynamic Rod Worth Measurement technique. The results of the startup physics testing program for Salem Unit 2 Cycle 11 follow. Critical boron, bank worth, and temperature coefficient measurement results are provided in Tables 1, 2, and 3, respectively. Comparisons to appropriate review and/or acceptance criteria are provided. Since review criteria are typically more restrictive than acceptance criteria for measured to predicted comparisons, only comparisons ~o the review criteria are provided if the review criteria are met since this guarantees that the acceptance criteria will also be met.
Table 1 Salem Unit 2 Cycle 11 Beginning of Life (BOL}, Hot Zero Power (HZP}, All Rods Out (ARO) Critical Boron Measurement Measured Value Design Value Review Criteria Sat/ Unsat (ppm)
(ppm)
Acceptance Range
(+/-50 ppm) 1684 1718 1668 - 1768 Sat
Document Control Del Table 2 LR-N99441 Salem Unit 2 Cycle 11 Dynamic Rod Worth Measurement (DRWM) Results Rod Bank Measured Design Value Review Sat/Unsat Worth (pcm)
Sat Table 3 Salem Unit 2 Cycle 11 BOL HZP ARO Isothermal Temperature Coefficient (ITC) Measurement and Inferred Most Limiting Moderatpr Temperature Coefficient (MTC)
<O Sat/Unsat Sat measured MTG value is corrected to the most limiting burnup for MTG (2000 MWD/MTU)
Document Control Def.
LR-N99441 Due to the satisfactory startup physics testing results* for Salem Unit 2 Cycle 11, power ascension was initiated. IN CORE flux map peaking factor measurement results (F ~H.
Fq, Fxy) with appropriate uncertainties applied as a function of core power level are provided in Tables 4, 5, and 6, respectively, which includes comparisons to the power level and/or core height dependent (Fq) Technical Specification and COLR limits for these parameters. Each part power flux map provided peaking factor results which met the Technical Specification and COLR limits for the flux map power level and the hot full power limits. Thus, power ascension was allowed up to 100 % power and the first near full power flux map occurred on June 7, 1999. This flux map showed acceptable comparisons to peaking factor limits as well with at least 8 % margin to the F ~H and Fxy Technical Specification and COLR limits and at least 22 % margin to the Fq Technical Specification and COLR limits.
Table 4 Salem Unit 2 Cycle 11 Nuclear Enthalpy Rise Hot Channel Factor (FN ~H) as a Function* of INCORE Map Power Level Near BOL Test Conditions Measured Values Required Value Sat/Unsat (Power) 1.65[1.0+0.3(1-P)]
14.2 %
1.5904
<2.0747 Sat 44.9%
1.5447
<1.9227 Sat 73.9%
1.5497
<1.7792 Sat 99.5%
1 ~5190
<1.6525 Sat Table 5 Salem Unit 2 Cycle 11 Maximum Heat Flux Hot Channel Factor (Fq(z)) asa Function of INCORE Map Power Level Near BOL Test Conditions Measured Required Sat/Unsat (Power)
Values Values*
14.2%
2.0959
<4.74 Sat 44.9%
1.9711
<4.7520 Sat 73.9%
1.9383
<3.2313
Sat 99.5%
1.8761
<2.4120 Sat Corresponds to hm1t at axial height with the highest Fq value Document Control Del Table 6 LR-N99441 Salem Unit 2 Cycle 11 Maximum Computed Radial Peaking Factor (F\\y) as a Function of INCORE Map Power Level and Rodded Condition for Surveilled Core Axial Heights Test Conditions Measured Values Required Values Sat/Unsat (Power) 14.2%