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MONTHYEARML20206K6391972-05-31031 May 1972 Ack Receipt of Re Technical Basis for Accepting Weld Surface Area W/Bluish Tint.No Further Questions Project stage: Other ML17278A2521985-06-26026 June 1985 Notification of 850627 Meeting W/Util & Exxon in Bethesda,Md to Identify & Clarify Preliminary Requirements for First Refueling of Plant Project stage: Meeting ML17278A3201985-07-26026 July 1985 Summary of 850627 Meeting W/Util & Exxon Nuclear in Bethesda,Md Re Util Plans & Preparations for Cycle 2 Core Reload Currently Scheduled for Spring 1986.List of Attendees & Viewgraphs Encl Project stage: Meeting ML17278A5751986-01-17017 January 1986 Proposed Tech Spec Table 3.8.4.3-1 Re Motor Operated Valves Thermal Overload Protection Project stage: Other GO2-86-081, Application for Amend to License NPF-21,changing Tech Specs to Add Auxiliary Steam & Fuel Pool Cooling Sys Valves to Update Table 3.8.4.3-1 Re Motor Operated Valves Thermal Overload Protection.Fee Paid1986-01-17017 January 1986 Application for Amend to License NPF-21,changing Tech Specs to Add Auxiliary Steam & Fuel Pool Cooling Sys Valves to Update Table 3.8.4.3-1 Re Motor Operated Valves Thermal Overload Protection.Fee Paid Project stage: Request GO2-86-113, Advises That Submittal of Base Licensing Amend Delayed Until 860301 Based on Recent Operating History.Suppl Will Be Submitted on 860501 to Address Actual Conditions.Spring Outage Scheduled for 860415 & Cycle 2 for 8606021986-01-30030 January 1986 Advises That Submittal of Base Licensing Amend Delayed Until 860301 Based on Recent Operating History.Suppl Will Be Submitted on 860501 to Address Actual Conditions.Spring Outage Scheduled for 860415 & Cycle 2 for 860602 Project stage: Other ML17278A8051986-03-31031 March 1986 Safety Review of WPPSS Nuclear Project 2 at Core Flow Conditions Above Rated Flow Throughout Cycle 1 & Final Feedwater Temp Reduction Project stage: Other GO2-86-311, Clarifies 860226 Application for Amend to License NPF-21, Revising Tech Specs to Support Operation of Plant at Full Rated Power During Cycle 2.Changes Discussed to Expedite Staff Review of Request1986-04-0707 April 1986 Clarifies 860226 Application for Amend to License NPF-21, Revising Tech Specs to Support Operation of Plant at Full Rated Power During Cycle 2.Changes Discussed to Expedite Staff Review of Request Project stage: Request GO2-86-367, Provides Supplemental Info Re 860226 Reload Summary Rept Concerning Changes in Expected Cycle 2 Reload Batch.Meeting Requested to Address NRC Concerns w/860520 Restart Date1986-04-24024 April 1986 Provides Supplemental Info Re 860226 Reload Summary Rept Concerning Changes in Expected Cycle 2 Reload Batch.Meeting Requested to Address NRC Concerns w/860520 Restart Date Project stage: Supplement GO2-86-370, Forwards XN-NF-85-138(P), LOCA Break Spectrum Analysis for BWR 5 & Affidavit for Withholding,In Support of Request for Amend to Tech Specs Re Cycle 2 Reload.W/O Rept1986-04-25025 April 1986 Forwards XN-NF-85-138(P), LOCA Break Spectrum Analysis for BWR 5 & Affidavit for Withholding,In Support of Request for Amend to Tech Specs Re Cycle 2 Reload.W/O Rept Project stage: Request GO2-86-381, Forwards NEDC-31107, Safety Review of WPPSS Nuclear Project 2 at Core Flow Conditions Above Rated Flow Throughout Cycle I & Final Feedwater Temp Reduction, Per 860226 Commitment1986-04-30030 April 1986 Forwards NEDC-31107, Safety Review of WPPSS Nuclear Project 2 at Core Flow Conditions Above Rated Flow Throughout Cycle I & Final Feedwater Temp Reduction, Per 860226 Commitment Project stage: Other ML17279A6481986-05-0101 May 1986 Draft Lead Test Assembly Program,Wpps 2 Project stage: Draft Other ML17278A8411986-05-22022 May 1986 Provides Supplemental Info to 860226 Application to Amend License NPF-21 Re Cycle 2 Reload.Use of Two Separate Sets for two-loop Operating Limits for Fuel Types & Separate Set for Single Loop proposed.Marked-up Tech Specs Encl Project stage: Supplement ML17278A8651986-05-23023 May 1986 Safety Evaluation Supporting Amend 27 to License NPF-21 Project stage: Approval ML17278A8631986-05-23023 May 1986 Amend 27 to License NPF-21,revising Tech Spec Table 3.8.4.3-1, Motor-Operated Valves Thermal Overload Protection, to Add Valves Previously Omitted,Add Valves Due to Sys Upgrades & Remove nonsafety-related Valves Project stage: Other ML17278A8481986-05-23023 May 1986 Safety Evaluation Supporting Amend 28 to License NPF-21 Project stage: Approval ML17278A8461986-05-23023 May 1986 Amend 28 to License NPF-21,revising Tech Specs to Support Operation of Facility at Full Rated Power During Cycle 2 & Establishing Operating Limits for All Fuel Types Project stage: Other ML17278A8801986-05-29029 May 1986 Offers No Comments on 860117,0226 & 0328 Requests for Amends to License NPR-21.Request for 1-yr Extension to Install Wetwell Level Monitoring Sys Acceptable But Installation Should Be Completed by Second Fuel change-out Project stage: Request GO2-86-060, Responds to Exxon Nuclear Corp 860617 Notification That NRC Considered Updated Hot Channel Delta CPR Methodology in Cotransa Model to Be Unreviewed.Addl Calculation Performed. No Further Action Necessary1986-06-27027 June 1986 Responds to Exxon Nuclear Corp 860617 Notification That NRC Considered Updated Hot Channel Delta CPR Methodology in Cotransa Model to Be Unreviewed.Addl Calculation Performed. No Further Action Necessary Project stage: Other 1986-04-25
[Table View] |
Text
ANTROLLEn Con TABLE 3. 8. 4. 3-:
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTiON VALVE NUMBER SYSTEM(S)
AFFECTED SYSTEM(S)
VALVE NUMBER AFFECTED ADD b
C.
CAC-V-2 CAC-V-4 CAC-V-6 CAC-V-8 CAC-V-11 CAC-V-13 CAC-V-15 CAC-V-17 CIA-V-20 CIA-V-30A CIA-V-30B FPC-V-153
'PC-V-154 FPC-V-156 Containment Atmospheric Control System Containment Instrument Air System Fuel Pool Cooling System g.
HSLC-V-1A MSLC-V-1B HSLC"V-1C MSLC-V-10 HSLC-V-2A MSLC-V-2B HSLC-V-2C MSLC-V-2D MSLC-V-3A HSLC-V-3B HSLC-V-3C MSLC-V-30 MSLC-V-4 MSI.C-V-5 MSLC-V-9 HS LC-V"10 Hain Steam Isolation Valve Leakage Control System HPCS-V-1 HPCS-V-4 HP CS-.V-10 HPCS-V-11 HPCS-V-12 HPCS-V-15 HPCS-V-23 High Pressure Core h.
Spray System'
-V-2 C-~g Reactor Closed Cooling Water
- -,System Deletel Cttot Safety Related LPCS-V-1 LPCS-V-5 LPCS" FCV-11 LPCS-V-12
'f.
tlS-V-1 HS-V-2 MS-V-5 AS"V-16 HS-V"19 HS-V-20 MS-V-67A t:,S-V-67B tlS-V-67C HS-V-67D PS-V-146 FWc-v-149 FP C-V-172 FP C-V-173 FPC-V-175 Low Pressure Core Spray System t1ain Steam System RC --
RCC-V-129 RCC-V"130 RCC-V-131 i.
RCIC-V-1 RCIC-V"8 RCIC.-V-10 RCIC-V-13 RCIC-V-19 RCIC-V-22 RCIC-V"31 FPC-V-181A FPC-V-181B Add due to Fuel Pool FPC-V-184 Cooling Modification and Upgrade Reactor Core Isolation Cooling System 860 1270203 8600>0<>>9>:
FDR ADOCf( 05000397 P
l..
<</>> o- <6
<<monQr ent
~
W
. ~ ~
~ ~
NTeOLLEO CO@
TABLE 3.8.4. 3-1 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION VALVE NUMBER SYSTEM(S)
AFFECTED SYSTEM(S)
VALVE NUMBER AFFECTED RCIC-V-45 RCIC.-V-46 RCIC-V-59 RCIC-V-63 RCIC-V-68 RCIC-Y-69 RCIC-V-76 RCIC-V-110 RCIC-V-113 j.
RFW-Y-65A RFW-V-658 k.
RHR-Y 3A RHR"V-38 RHR-V-4A RHR-Y-48 RHR-V-4C RHR-Y-6A RHR-Y-68 RHR-V-8 RHR-V-9 RHR-V-16A RHR-V-168 RHR-V-17A RHR-V-178 RHR-V-21 RHR-V-23 RHR-Y-24A RHR-V"248 RHR-Y-27A RHR-V-278 RHR-Y"40 RHR"Y-42A RHR"V"428 Reactor Core Isolation Cooling System Reactor Feedwater System Residual Heat Removal System RHR-Y-42C RHR-V-47A RHR-Y"478 RHR-Y-48A RHR-Y-488 RHR-V-49 RHR-V-53A RHR-V-538 RHR-V-64A RHR-V"648 RHR-V 64C RHR-Y-68A RHR-V-688 RHR-V-7 RHR-V-A RHR-V-748 RHR-Y-115 RHR-V-116 RHR-V"123A RHR-V-1238 RHR"V"134A RHR-V-1348 RRC-V-16A R'ACU-Y"1 RWCU-Y"4 CU~4-
~~S-V-68
< S-V-.6SB DD H -Y-7 Reactor Recirculation System DEL'ETE
- Not Safety Related Reactor Water Cleanup System DELETE
~Not Safety Related ADD".,
Installed'per Design Change
TABLE 3.8.4.3-1 (Continued)
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION VALVE NUMBER
%MCUS~~
RWNW&0 n.
SGT-V-1A SGT V-18 SGT-V-3Al SGT V 3A2 SGT-V-3B1 SGT-V-3B2 SGT-V-4A1 SGT V 4A2 SGT-V-481 SGT-V-482 SGT-V-5AI SGT-V~5A2 SGT-V-581 '-
SGT V-582 SYSTEM(S)
AFFECTED Reactor Water Cleanup System DELETE Not Sal'ety Pelated Standby Gas Treatment System BIVALVE NUMBER o.
p.
SW-V-2A SW-V-28 SW-V 4A SW-V-48 SW-V 4C SW"V 12A SW V-128 SW V 24A SW V 248 SW V-24C SW-V-29 SW-V-44 SWW-698-SH~
%7 SW-V 758 SW-V-90 SW-V 187$
SW-V-18 SW-V-188B'YSTEM(S)
AFFECTED Standby Liquid Control System Standby Service Water System DELE,TE.
Valves Deactivated per Design Change WASHINGTON NUCLEAR - UNIT 2 3/4 8-28
I i
~~ Ms