ML20207R280
| ML20207R280 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/10/1987 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2NRC-7-046, 2NRC-7-46, TAC-65027, NUDOCS 8703170054 | |
| Download: ML20207R280 (3) | |
Text
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- o. 2 Unit Project Organization Telecopy ( 1 643 5 Ext.160 P.O. Box 328 March 10, 1987 Shippingport, PA 15077 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
REFERENCE:
Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Status of Closure of SER Confirmatory Items Our records at this time indicate that the following DLC action is required to permit closure.
Projected Date of Submittal to item Number Subject NRC 2
Differential Settlement of Letter 3/16/87 buried pipe 3
Internally generated missiles FSAR Amend #16 inside containnent 4/1/87 4
Internally generated missiles FSAR Amend #16 outside containnent 4/1/87 6
Analysis of Pipe Break Protection FSAR Amend #16 Outside Containment 4/1/87 7
FSAR drawings of pipe break FSAR Amend #16 locations 4/1/87 8
Results of Jet Impingement effects FSAR Amend #16 4/1/87 11 NUREG-0737 Pressure / Relief Valve Letter Provide more information on 3/27/87 over pressure report 22 Natural Circulation - Compare After Fuel Load BV-2 with Diablo Canyon 26 Centainment Sump 50% blockage Letter Provide analysis of quantity of 3/27/87 insulation
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United States Nuclear Regulatory Commission Status of Closure of SER Confirmatory items Page 2 Projected Date of Submittal to item Number Subject NRC 28 IE Bulletin 80-06 (ESFAS Test)
Will perform after fuel load 32 Control System Failure - Malfunction 3/27/87 of Common Power Source - Provide info on FW Flow Control 34 Voltage Analysis - Station Service Test complete voltage dip - perform test results satisfactory 35 Incorporation of GDC 50 question FSAR Amend #16 response in FSAR Chapter 8 -
4/1/87 Electrical Penetrations 36 Complete core damage estimation Letter 3/16/87 procedur e 37 Training Program for operation and Training Program maintenance of diesel generators Procedures Completed 38 Test Vibration of instruments and Test scheduled 3/17/87 controls on diesel generator 40 Solid Waste process control program After prepare progran Fuel Load 41 TM1 Action (a) Reactor coolant leakage outside Complete prior to fuel containment - Write procedure load (b) Mitigation of LOCA/ Loss Feedwater Complete prior to fuel Write Procedure load (c) Reactor coolant pump trip criteria 3/27/87 (d) Record ECCS Outage - Write Complete prior to fuel procedure load 46 Control Room Isolation - Hi Radiation 3/13/87 Signal - Provide design information 47 Prepar e Procedures Generation Package Prepare Package 3/27/87
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United States Nuclear Regulatory Commission Status of Closure of.SER Confirmatory items Page 3 Projected Date of Submittal to item Number Subject NRC 52 Initial Testing - Provide additional Data (a) Accumulator isolation valve Will be resolved with closure test Tech Spec Review (b) 50V, PS, 15 tests In FSAR Amend #13 (c) Plant Performance after MSIV in FSAR Amend #15
. c losur e (d) Steam extraction system In FSAR Amend #15 DUQUESNE LIGHT COMPANY By X J./Carey V
Senior Vice President cc:
Mr. P. Tam, Project Manager Mr. J. Beall, NRC Sr. Resident inspector Ms. A. Asars, NRC Resident inspector INP0 Records Center NRC Document Control Desk