ML20137Q816
| ML20137Q816 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/04/1986 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.G.1, TASK-2.D.1, TASK-2.F.1, TASK-2.F.2, TASK-2.G.1, TASK-2.K.1, TASK-2.K.3.05, TASK-2.K.3.17, TASK-2.K.3.31, TASK-3.D.1.1, TASK-TM 2NRC-6-011, 2NRC-6-11, NUDOCS 8602070030 | |
| Download: ML20137Q816 (9) | |
Text
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3 11 esne Light mer Nuclear Construction Division Telecopy 29 N'"u*g"O*I'is"2$s**'*""'*
February 4, 1986 United States Nuclear Regulatory Conmission Washington, DC 20555 ATTENTION:
Mr. Lester S. Rubenstein, Director PWR Project Directorate No. 2 Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 S.E.R. Outstanding Issues Status Gentlenen:
Attached are three current lists, as of Decenber 31, 1985, which provide our understanding of outstanding issues.
Itens identified as "conplete" are those for wnich responses have been provided and no confir-mation of status has yet been received fran the staff.
We consider these itens satisf actorily closed unless notified otherwise.
In order to pennit timely resolution of itens identified as "conpl ete" which may not be resolved to the staff's satisfaction, please provide a specific description of the issue which renains to be resolved.
Itens identified as "confinna-tory" are based upon fonnal or infonnal conmunications or agreenents with the staff.
Please infonn us of any disagreenent of status described on the attached list.
DUQUESNE LIGHT COMPANY W
By V
J."J.Narey Vice President TRS/wjs At t actrnents cc:
Mr. P. Tam, Project Manager (w/ attachments)
Mr. W. Troskoski, Sr. Resident Inspector (w/attachnents)
Mr. G. Walton, NRC Resident Inspector (w/ attachments) 9602070030 860204 PDR ADOCK 0500 2
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ATTACHMENT 1 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 1.2 OPEN ISSUES 1
ITEM RESPONSE DATE NO.
ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 1.
Preservice/ Inservice Testing (3.9.6)
Open 2NRC-5-154,12/26/85 04/01/86 2.
Pump an Valve Leak Testing (3.9.6)
Conplete 2NRC-6-005,01/09/86 3.
ICC Instrtsnentation (Iten II.F.2 of NUREG 0737)(4.4.7)
Open 2NRC-5-079,05/31/85 TBD 4.
Preservice/ Inservice Inspection Progran (5.2.4.3;-5.4.2.2; 6.6)
Open 2NRC-5-154, 12/26/85 12/31/86 5.
Safe and Alternate Shutdown (9.5.1)
Open 08/86 6.
Management and Organi-zation(13.1)
Open TBD 7.
Cross-Training Progran Carey to R. M. Keller (13.2.1.2)
Conplete Letter 06/13/85 8.
Emergency Preparedness Plan (13.3.3)
Open 2NRC-5-077, 05/28/85 07/86 NRR Review of PGP for E0Ps (13.5.2)
Conpl ete NRR Acgion Only 9.
Initial Test Progr'an (14)
Open TBD
- a. Renote Shutdown Test Complete 2NRC-5-110,07/29/85
(
- b. Test Acceptance Criteria Conplete 2NRC-5-110,07/29/85
- c. NUREG 0737 Item I.G.1 Complete 2NRC-5-110,07/29/85
- d. Relief and Dump Valve Capacity Tests Conplete 2NRC-5-110, 07/29/85
- e. Test Classification Discrepancies Conplete 2NRC-5-110,07/29/85
- f. Accumulator Isolation Valve Test Conplete 2NRC-5-110,07/29/85
- g. Condenser Hotwell Level Systen Test Conplete 2NRC-5-110,07/29/85
ITEM RESPONSE DATE NO.
_ ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE)
- h. Safety Injection Pump Test Open 07/86
- 1. Turbine Plant CCW Test Schedule Open 07/86 10.
Contol Room Design Review (18.1)
Canplete 2NRC-5-147, 12/02/85 11.
Safety Paraneter Display System (18.2)
Open 2NRC-5-151, 12/20/85 TBD Iten was found in text but not in Table 1.2.
TBD To be detennined.
~ - - -.
ATTACHMENT 2 SAFETY EVALUATION REPORT REVIEW STATUS TABLE l.4 CONFIRMATORY ISSUES ITEM RESPONSE DATE NO.
ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 1.
Operating Procedures for Continuous Conmuni-cation Links (2.2.2)
Open 06/30/86 2.
Differential Settlenent of Buried Pipes (2.5.4.3.3)
Open 06/30/86 3.
Internally Generated Missiles (Outside Con-tainnent) (3.5.1.1)
Open 4.
Internally Generated Missiles (Inside Con-tainnent) (3.5.1.2)
Open 5.
Turbine Missiles (3.5.1.3)
Open 6.
Analysis of Pipe Break Protection Outside Con-tainnent (3.6.1)
Open 7.
FSAR Drawing of Break Locations (3.6.2)
Open 8.
Results of Jet Impinge-ment Effects (3.6.2)
Open 9.
Soil Structure Inter-2NRC-5-ll4,08/07/85 action Analysis (3.7.3)
Conplete 10.
Design Docunentation of ASME Code Conponents (3.9.3.1)
Conplete 2NRC-6-001, 01/03/86 11.
Item II.D.1 of NUREG 0737 (3.9.3.2)
Open TBD 12.
Seismic and Dynaritic Qualification of Mechanical and Electri-cal Equipnent (3.10.1)
Open 07/30/86
, ITEM RESPONSE DATE NO.
ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT C0W LETE) 13.
Pump and.'alve Oper-ability Assurance (3.10.2)
Open 07/30/86 14.
Environmental Qualifi-cation of Mechanical and Electrical Equip-ment (3.11)
Open 07/30/86 15.
Peak Pellet Design Basis (4.2.1)
Complete 2NRC-5-132,09/13/85 16.
Discrepancies in the FSAR (4.2.2)
Complete 2NRC-5-132,09/13/85 17.
Rod Bowing Analysis
~
(4.2.3.1[6])
Conplete 2NRC-4-102,07/12/84 18.
Fuel Rod Internal Pres--
sure (4.2.3.1[8])
Couplete 2NRC-5-132,09/13/85 19.
Predicted Cladding Col-1 apse Time (4.2.3.2[2])
Conplete 2NRC-5-132,09/13/85 20.
Use of the Square-Root-o f-the-Sum-of-the-Squares Methoo for Seismic and LOCA Load -
Calculation (4.2.3.3[4])
Canplete 2NRC-4-209, 12/18/84 21.
Analysis of Canbined Loss-of-Cool ant-Acci-dent and Seismic Loads (4.2.3.3[4])
Conplete 2NRC-5-002,01/03/86 22.
Natural Girculation 2NRC-5-157, 12/24/85 Compl ete NRR Action On,1y Test.(5.4.7.5) 23.
Reactor Coolant System High Point Vents (5.4.12)
Open 2NRC-5-157,12/24/85 TBD 24.
Blowdown Mass and Energy Release Analysis Methodology (6.2.1.1; 6.2.1.3; 6.2.1.4)
Coupl ete NRR Action Only 25.
Containment Sump 50%
Blockage Assunption (6.2.2)
Open TBD' ITEM RESPONSE DATE NO.
ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 26.
Design Modification of Autanatic Reactor Trip Using Shunt Coil Trip Attactinent (7.2.2.3)
Open 06/31/86 27.
Autanatic Opening of Service Water Systen Valves MOV ll3C and 1130 (7.3.3.10)
Open 2NRC-5-157, 12/24/85 TBD Zd.
IE Bulletin 80-06 Con-cerns (7.3.3.13)
Canpl ete NRC Action Only 29.
NUREG 0737 Item II.F.1, Accident Monitoring Instrumentation Posi-2NRC-4-210, 12/18/84 tions (7.5.2.2)
Complete 2NRC-5-157, 12/24/85 30.
Bypass and Inoperative Status Panel (7.5.2.4)
Canpl ete NRC Action Only 31.
Revision of the FSAR:
Cold Leg Accumulator Motor-Operated Valve Position Indication (7.6.2.4)
Open TBD 32.
Control Systen Failure Caused by Malfunction of Common Power Source or Instrument Line (7.7.2.3)
Open 2NRC-5-141, 10/15/85 33.
Confirmatory Site Visit Open TBD
- a. Independence of Offsite
~ Power Circuits Between the Switchyard and Class IE Systen (8.2.2.3)
- b. Confinnatory of the Protective Bypass (8.3.1.2)
- c. Verification of DG Start and Load Tests (8.3.1.8)
- d. DG Load Capability Qualification Test (8.3.1.9)
- e. Margin Qualification Test (8.3.1.10)
ITEM RESPONSE DATE NO.
ISSUE DLC STATUS LETTER NO. AND DATE,_
(IF NOT COMPLETE)
- f. Electrical Interconnec-tion Between Redundant Class lE Buses (8.3.1.13)
- 9. Verification of Elec-trical Independence Between Power Supplies to Controls in Control Room and Renote Loca-tions (8.3.3.5)
Lighting Audit (9.5.3.3) 34.
Voltage Analysis --
Aprox 6 Mths Prior to Fuel l
Verification of Test Fuel Load Results (8.3.1.1)
Open 35.
Description and Analy-sis of Conpliance with Amendment 12 GDC 50 (8.3.3.7.1)
Open 36.
Completion of Plant-Specific Core Danage Estimate Proceoure Before Fuel Load 12/31/86 (9.3.2.2)
Open 37.
Training Progran for the Operation and Maintenance of the Diesel Generators TBD (9.5.4.1)
Open 38.
Vibration of Instru-ments and Controls.on Diesel Generators TBD' (9.5.4.1)
Open 39.
Surveillance of Lube Oil Level in Diesel Generator Rocker Ann Lube Oil Reservoir TBD (9.5.6)
Open 40.
Solid Waste Process Control Progran 09/30/86 (11.4.2)
Open
ITEM RESPONSE DATE NO.
ISSUE OLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 41.
TMI Action Plan Items
- a. III.D.l.1 (13.5.2)
Open TBD D. II.K.l.5 and II.K.l.10 (15.9.2; 15.9.3)
Coupl ete 2NRC-5-157, 12/24/85
- c. II.K.3.5 (15.9.9)
Couplete No Action Required
- d. II.K.3.17 (15.9.11)
Coupl ete 2NRC-5-157, 12/24/85
- e. II.K.3.31 (15.9.14)
Conplete WCAP-10054 WCAP-10079 42.
Plant-Specific Dropped Rod Analysis (15.4.3)
Open 04/01/86 43.
Steam Generator Tube Rupture (15.6.3)
Open 03/01/86 44.
Quality Assurance Pro-2NRC-5-096,06/28/85 gran (17.5)
Closed 2NRC-5-152, 12/20/85 Hazards analysis is scheduled for conpletion at the end of 1986 and docunented in early 1987.
TBD To be determined.
Item was found in text but not in Table 1.4.
7
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ATTACHMENT 3 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 16.0 TECHNICAL SPECIFICATONS ITEM DLC NO.
ISSUE STATUS LETTER N0. AND DATE REMARKS 1.
Initial Draft Subnittal Complete 2NRC-4-144, 09/14/84 Awaiting NRC Action Pre-Issue Revision 1 Complete 2NRC-5-153, 12/20/85 Awaiting NRC Action 1