ML20206J666

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Forwards Lists of Current Understanding of Outstanding SER Issues Status.Specific Description of Any Issue Identified as Complete Which NRC Does Not Consider Complete Requested
ML20206J666
Person / Time
Site: Beaver Valley
Issue date: 06/19/1986
From: Carey J
DUQUESNE LIGHT CO.
To: Harold Denton, Tam P
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.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-6-065, 2NRC-6-65, IEB-80-06, IEB-80-6, NUDOCS 8606270238
Download: ML20206J666 (10)


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'Af Ducluesrie Udit 2NRC-6-065 Seaver Valley No. 2 Unit Project Organf ration SEG Sulldin9 (412) 643-5200 k hp pfrt. PA * #

15077 t i June 19, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Mr. Peter Tam, Project Manager Division of PWR Licensing - A Office of Nuclear Reactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 S.E.R. Outstanding Issues Status Gentlemen:

Attached are four current lists, as of June 1,1986, which provide our understanding of outstanding issues. Items identified, as " complete" are those for which responses have been provided and no confirmation of status has yet been received from the staff. We consider these items satisfactorily closed unless notified otherwise. In order to permit timely resolution of items identified as " complete" which may not be resolved to the staff's satisfaction, please provide a specific description of the issue which remains to be resolved. Items identified as " confirmatory" are based upon formal or informal conniunications or agreements with the staff.

Please inform us of any disagreement of status described on the attached list.

DUQUESNE LI FT COMPANY I

f By /

G/arey (/

J(){Pfesident Vice RWR/ sip NR/SER/ LETTER 8606270238 860619 PDR ADOCK 0D000412 Attachments cc: Mr. W. Troskoski, Resident Inspector (w/ attachments)

Mr. G. Walton, Resident Inspector (w/ attachments) s

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ATTACHMENT 1 SAFETY EVALUATION REPORT REVIEW STATUS i TABLE 1.2 OPEN ISSUES 4

ITEM RESPONSE DATE i NO. ISSUE DLC STATUS LETTER NO. AND DATE (lF NOT COMPLETE)

1. Preservice/ Inservice Complete 2NRC-5-154, 12/26/85 Testing (3.9.6) 2NRC-6-034, 04/09/86 2 Pump and Valve Leak Complete 2tHC-6-005, 01/09/86 Testing (3.9.6)

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3. ICC instrumentation Complete 2NRC-5-079, 05/31/85 (item II.F.2 of NIREG 2NRC-6-037, 04/11/86 0737) (4.4.7) 4 Preservice/ inservice Open 2NRC-5-154, 12/26/85 03/31/97 Inspection Program (5.2.4.3; 5.4.2.2; 6.6)

, 5. Safe and Alternate Open 08/86 Shutdown (9.5.1) 6 Management and Organi- Open 09/86 j zation (13.1) 7 Cross-Training Program Confirmatory Carey to R. M. Keller (13.2.1.2) 45 Letter 06/13/85

8. Emergency Preparedness Open 2tHC-5-077, 05/28/85 07/86 Pian (13.3.3)
9. Initial Test Program (14)
a. Remote Shutdown Test Open 2NRC-5-110, 07/29/85 06/86*

D. Test Acceptance Closed 2NRC-5-110, 07/29/85

. Criteria

c. N'JREG 0737 Item 1.G.1 Open 2NRC-5-110, 07/29/85 06/86*
d. Relief and Dump Valve Complete 2NRC-5-110, 07/29/85 l Capacity Tosts 2NRC-64)45, 05/06/86 l
e. Test Classification Closed 2NRC-5-110, 07/29/85 Di screpancies
f. Accumulator isolation Open 2NRC-5-110, 07/29/85 06/86*

Valve Test l

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j ITEM RESFONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT 00r LETE)

g. Condenser Hotwell Level Open 2mC-5-110, 07/29/85 06/86*

System Test

h. Safety injection Pump Open 06/86*

Test 1 Turbine Plant CCW Test Open 06/86*

Schedule 10 Control Room Design Open 2mC-5-147, 12/02/85 01/87 Review (18.1) 11 Safety Parameter Complete 2*C-5-151, 12/20/8 5 Display System (18.2 22C-6-033, 04/09/86 4

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  • To be included in FSAR Amendment 12, June 1986

} TBD To be determined.

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ATTACHMENT 2 SAFETY EVALUATION REPCRT REVIEW STATUS TABLE 1.4 CONFlRMATORY ISSLES ITEM RESR)NSE DATE NO. ISSUE DLC STATUS LETTER NO. ANI) DATE (IF NOT C06FLETE) 1 Operating Procedures Open 06/30/86 for Continuous Communl-cation Links (2.2.2) 2 Differential Settlement Open 06/30/86 of Buried Pipes (2.5.4.3.3)

3. Internally Generated Open Missiles (Outside Con-tainment) (3.5.1.1) 4 Internally Generated Open Missiles (Inside Con-tainment) (3.5.1.2) 5 Turbine Missiles Open 2mC-5-157,12/24/85 01/30/87 (3.5.1.3) 6 Analysis of Pipe Break Open
  • Protection Outside Con-tainment (3.6.1) 7 FSAR Drawing of Break Open Locations (3.6.2)

Results of Jet Impinge- Open

  • 8.

ment Ef fects (3.6.2) 9 Soll Structure inter- Closed 2mC-5-114, 08/07/85 action Analysls.(3.7.3)

10. Design (bcumentation of Complete 2mC-6-001, 01/03/86 ASME Code Compotents 2 *C-6-061, 06/06/86 (3.9.3.1) 11 Item II.D.1 of NUREG Complete 2mC-5-157,12/24/8 5 0737 (3.9.3.2)
12. Selsnic and Dynamic Open 07/30/86 Quellficatico of Mechanical and Electrl-cal Equipment (3.10.1)

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. ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT CO*LETE) 13 Pump and Valve Oper- Open 07/30/86 ability Assurance (3.10.2)

J 14 Environmental Quallft- Open 07/30/86 cation of Mechanical and Electrical Equip-ment (3.11) j 15. Peak Pellet Design Closed 2mC-5-132. 09/13/85 Basis (4.2.1) i 16 Discrepencies in the Closed 2mC-5-132, 09/13/85 FSAR (4.2.2) i 17 Rod Bowing Analysis Closed 2*C-4-102, 07/12/84 (4.2.3.1161) i 18 Fuel Rod Internal Pres- Closed 22C-5-132, 09/13/85 sure (4.2.3.1181) 19 Predicted Cladding Col- Closed 2*C-5-132, 09/13/85 lapse Time (4.2.3.2121) i

20. Use of the Square-Root- Closed 2*C-4-209,12/18/84 of-the-Sum-of-the-Squares Method for

, Seismic and t.0CA Load Calculation (4.2.3.3141) l 21 Analysis of Combined Complete 2mC-6-002, 01/03/86 ,

Loss-of-Coolant-Acci-dont and Seismic dLoads (4.2.3.3141) 22 Natural Circulation Open 2mC-5-157,12/24/85 12/31/86 l Test (5.4.7.5) m R Action Only

23. Reactor Coolant System Open 2mC-5-157,12/24/85 09/30/86 I

High Point Vents (5.4.12) 24 Blowdown Mass and Complete ER Action Only Energy Release Analysis Methodology (6.2.1.1; l 6.2.1.3; 6.2.1.4) l

25. Containment Sump 50% Complete 2mC-5-157, 12/24/85 Blockage Assumption 2mC-6-059, 06/06/86 (6.2.2) en l

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i ITEM RESPONSE DATE i

N). ISSUE DLC STATUS LETTER NO. AlO DATE (IF NOT COWLETE) 26 Design Modt fication of Open 07/31/86 Automatic Reactor Trip Using Shunt Coll Trip Attachment (7.2.2.3) 27 Automatic Opening of Closed Amend. 10, 05/30/85 Service Water System 2mC-5-157, 12/24/85 Valves MOV 113C and 1130 (7.3.3.10) 1

28. IE Bulletin 80-06 Con- Open 12/31/86
cerns (7.3.3.13) 29 NUREG 0737 Item II .F.1, Closed 2mC-4-210,12/18/84 Accident Monitoring 2mC-5-157, 12/24/85 Instrumentation Posl-tions (7.5.2.2)

) 30 Bypass and inoperative Complete 2mC-6-038, 04/15/86 Status Panel (7.5.2.4) 31 Revision of FSAR: Open 06/30/86'**

Cold Leg Accumulator Motor-Operated Valve Position Indication (7.6.2.4) 32 Control System Fallure Complete 2mC-5-141, 10/15/85 Caused by Mal function 2*C-6-054, 05/28/86 of Common Power Source or instrument Line (7.7.2.3)

33. Confirmatory Site Visit
a. Independence of Of f site Closed Power Circuits Between the Switchyard and Class i IE System (8.2.2.3)
b. Confirmatory of the Closed Protective Bypass (8.3.1.2)
c. Verification of DG Closed Start and Load Test (8.3.1.2)
d. DG Load Capability Closed Quallfit ition Test 4

(8.3.1.9) 7

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. -4 ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COWLETE)

e. Margin Qualification Closed Test (8.3.1.10)
f. Electrical Interconnec- Closed tion Between Redundant Class IE Buses (8.3.1.13)
g. Verification of Elec- Closed trical Independence Between Power Supplies to Controls in Control Room and Remote Loca-tions (8.3.3.5)
    • Lighting Audit (9.5.3.3) 34 Voltage Analysis -- Open Approx. 6 Months verificaton of Test Prior To Fuel Results (8.3.1.1) Load 35 Description and Analy- Open 07/31/86 sls of Compilance with
GOC 50 (8.3.3.7.1) i 36 Completion of Plant- Open 12/31/86 SpectfIc Core Damage Estimate Procedure Before Fuel Load j (9.3.2.2)

! 37 Training Pro;.*am for Open 12/86 the Operation and Maintenance of the Diesel Generators i (9.5.4.1) 38 Vibration of instru- Open TBD ments and Controls on Diesel Generators (9.5.4.1)

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. 39 Surveillance of Lube Complete 2*C-6-029, 03/26/86 Oil Level in Diesel Generator Rocker Arm Lube Oil Reservoir (9.5.7)

. ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (lF NOT CO*LETE) 40 Solid Weste Process Open 09/30/86 Control Program (11.4.2) 41 TMl Action Plan items

a. I l l .D.1.1 (13.5.2) Open TBD
b. I I .K.1.5 a nd l l .K.1.10 Complete 2 mC-5-157, 12/24/85 (15.9.2; 15.9.3)
c. I I .K.3.5 ( 15.9.9) Complete No Action Required l d. II.K.3.17 (15.9.11) Complete 2mC-5-157,12/24/85 i
e. I I .K.3.31 ( 15.9.14) Complete CAP-10054
WCAP-10079

. 42 Plant-Specific Dropped Complete 2*C-6-030, 04/01/86 1

{ Rod Analysis (15.4.3) l i 43. Steam Generator Tube Open SGTR-86-001, 02/23/86 Rupture (15.6.3) 44 Quality Assurance Closed 2mC-5-096, 06/28/85 Program (17.5) 2mC-5-152, 12/20/86 45 Cross-Training Program Open T80 46 Control Room isolation Open 08/15/86 On High Radiation Signal i

ER Review of PGP for mR Action Only 47 Complete E0Ps (13.5.2)

  • Hazards analysis Is scheduled for completion at the end of 1986 and documented In early 1987.
    • Item was found in text but not in Table 1.4 es* To be included in FSAR Anendment 12, June 1986 TBD To be detennined.

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ATTACHNENT 3 SAFETY EVALUATION REP (RT REVIEW STATUS TABLE 16.0 TEONICAL SPECIFICATIONS ITEM NO. ISSUE DLC STATUS LETTER NO. AND DATE REMARCS 1 Initial Draft Sutnittal Complete 2mC-4-144, 09/14/84 Auelting E C Action

2. Pre-issue Revision I Complete 2mC-5-153, 12/20/85 Awelting R C Action I

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.. I ATTACHMENT 4 REQtEST FOR ADDITIONAL INFORMATION l RESPONSE DATE DATE SUBJECT DLC STATUS LETTER NO. AND DATE (IF NOT C0hPLETE) 03/03/86 Inadequate Core Cooling Complete 2mC-6-037, 04/11/86 04/09/86 Technical Specifications Complete 2mC-6-044, 05/06/86 -

04/22/86 RCP Trip Criteria TBD 05/23/86 Control Room Isolation 08/15/86 On High Radiation i

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