ML20211B324

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Forwards Lists,Identifying Status of Open & Confirmatory SER Issues & Tech Specs
ML20211B324
Person / Time
Site: Beaver Valley
Issue date: 10/09/1986
From: Carey J
DUQUESNE LIGHT CO.
To: Harold Denton, Tam P
Office of Nuclear Reactor Regulation
References
2NRC-6-107, NUDOCS 8610170191
Download: ML20211B324 (11)


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2NRC-6-107 Beaver VaHoy No. 2 Unit Project Organization Telecopy 35 Ext.160 f,h,G Bj2 October 9, 1986 Shippingport, PA 15077 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 five current lists, as of September 23, 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 satisf actorily 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 communications or agreements with the staff. Please inform us of any disagreement of status described on the attached list.

DUQUESNE LIGHT COMPANY By J. J. Carey Sr. Vice President RWR/ijr NR/ ISSUE / STATUS Attachments AR/NAR cc: Mr. J. Beall, Senior Resident Inspector - w/ attachments Mr. L. Prividy, Resident Inspector - w/ attachments 8610170191 86100, 60l

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,, ATTACHMENT 1 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 1.2 OPEN ISSUES ITEM s RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF 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 2NRC-6-005, 01/09/86 Testing (3.9.6)
3. ICC Instrumentation Closed 2NRC-5-079, 05/31/85 (Item II.F.2 of NUREG 2NRC-6-037, 04/11/66 0737) (4.4.7) 4 Preservice/ Inservice Open 2NRC-5-154, 12/26/85 03/31/87 Inspection Program (5.2.4.3; 5.4.2.2; 6.6)
5. Safe and Alternate Open 12/15/86 Shutd own (9.5.1) 6 Management and Organi- Under tRC 2NRC-6-097, 09/18/86 zation (13.1) Rev i ew
7. Cross-Training Program Con fi rmatory Carey to R. M. Kel ler (13.2.1.2) 45 Letter 06/13/85 8 Emergency Preparedness Closed 2NRC-5-077, 05/28/85 Plan (13.3.3) 2NRCW6-092, 08/22/85
9. Initial Test Program (14)
a. Remote Shutdown Test Complete 2NRC-5-110, 07/29/35 .

2NRC-6-066, 06/20/86

b. Test Acceptance Closed 2NRC-5-110, 07/29/85 Criteria
c. NUREG 0737 Item 1.G.1 Complete 2NRC-5-110, 07/29/85 2NRC-6-066, 06/20/86
d. Rollet and Dump Valve Complete 2NRC-5-110, 07/29/85 Capacity Tests 2NRC-6-045, 05/06/86
e. Test Classi fication Closed 2NRC-5-110, 07/29/85 Di sc repa ncies
f. Accumulator I solation Complete 2NRC-5-110, 07/29/85 Val ve Test 2NRC-6-066, 06/20/86

ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT C00FLETE)

g. Condenser Hotwell Level Complete 2NRC-5-110, 07/29/85 Systen Test 2NRC-6-066, 06/20/86 2NRC-6-070, 06/27/86
h. Safety injection Pump Complete 2NRC-6-066, 06/20/86 Test I. Turbine Plant CCW Test Complete 2NRC-6-066, 06/20/86 Sched ule 10 Control Room Design Open 2NRC-5-147, 12/02/85 01/87 Review (18.1) 11 Safety Parameter Complete 2NRC-5-151, 12/20/85 Display Systen (18.2) 2NRC-6-033, 04/09/86 2NRC-6-064, 06/16/86 9

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ATTACHNENT 2 SAFETY EVALUATION REPORT REVI EW STATUS TABLE 1.4 CONFIRMATORY ISSUES ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 1 Operating Procedures Complete 2NRC-6-078, 08/04/86 har Continuous Conmunl- 2NRC-6-091, 08/19/86 cation Links (2.2.2)

2. Differential Settlement Open 10/31/86 of Buried Pi pes (2.5.4.3.3)

' 3. Internally Generated Open

  • Mi ssiles (Outside Con-tai nment) (3.5.1.1) 4 Internally Generated Open Mi ssiles (Inside Con-tainment) ( 3. 5.1.2 )
5. Turbine Missiles Open 2NRC-5-157, 12/24/85 01/30/87 (3.5.1.3)
6. Analysis of Pipe Break Open
  • Protection Outside Con-tai nment (3.6.1)
7. FSAR Drawing of Break Open Locations (3.6.2)
8. Results of Jet Impinge- Open
  • ment Ef fects (3.6.2) 9 Soll Structure Inter- Closed 2NRC-5-114, 08/07/85 action Analysis (3.7.3)
10. Design Documentation of Closed 2NRC-6-001, 01/03/86 A94E Code Conponents 2NRC-6-061, 06/06/86 (3.9.3.1)
11. Item I I.D.1 of NUREG Complete 2NRC-5-157, 12/24/85 0737 (3.9.3.2)
12. Selsmic and Dynamic Open 2NRC-6-057, 06/04/86 09/20/86 Quali fication of 2NRC-6-076, 08/04/86 Mechanical and Electri-cal Equi pment (3.10.1) t

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

13. Pump and Valve Oper- Open 2NRC-6-057, 06/04/86 09/30/86 ability Assurance 24RC-6-076, 08/09/86 (3.10.2)-

14 Environmental Quellfl- Open 2NRC-6-053, 05/23/86 10/20/86 cation of Mechanical and Electrical Equip-ment (3.11)

15. Peak Pellet Design Closed 2NRC-5-132, 09/13/85 Basi s (4.2.1)
16. Di screpancies In the Closed 2NRC-5-132, 09/13/85 FSAR (4.2.2) 17 Rod Bowing Analyris Closed 2NRC-4-102, 07/12/84 (4.2.3.1161)
18. Fuel Rod Internal Pres- Closed' 2NRC-5-132, 09/13/8 5 sure (4.2.3.1181) 19 Predicted Cladding Col- Closed 2NRC-5-132, 09/13/85 lapse Time (4.2.3.2121)
20. Use of the Square-Root- Closed 2NRC-4-209,12/18/84 of-t he-Sum-of-t he-Squares Method for Seismic and LOCA Load Calculation (4.2.3.3141) 21 Analysis of Combined Complete 2NRC-6-002, 01/03/86 Los s-o f-Coola n t- Acci-dont and Seismic dLoads (4.2.3.3141)
22. Natural Circulation Open 2NRC-5-157, 12/24/85 12/31/86 Test ( 5.4.7.5)
23. Reactor Coolant System Open 2NRC-5-157, 12/24/85 12/31/86 High Point vents (5.4.12) 24 Blowdown Mass and Complete NRR Action Only Enongy Release Analysis

! Methodology (6.2.1.1; 6.2.1.3; 6.2.1.4)

25. Containment Sump 50% Open 2NRC-5-157, 12/24/85 12/31/86 Blockage Assumption 2NRC-6-059, 06/06/86 1

(6.2.2) 1

ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 26 Design Modification of Complete 2NRC-6-067, 06/23/86 Automatic Reactor Trip Using Shunt Coll Trip Attachment (7.2.2.3)

27. Automatic Opening of Closed Amend. 10, 05/30/85 Service Water Systen 2NRC-5-157, 12/24/85 Valves MOV 113C and 113D (7.3.3.10)
28. IE Bulletin 80-06 Con- Open 12/31/86 cerns (7.3.3.13)
29. NUREG 0737 Item l i.F.1, Closed 2NRC-4-210, 12/18/84 Accident Monitoring 2NRC-5-157,12/24/85 Instrumentation Post-t ions (7.5.2.2)
30. Bypass and inoperative Complete 2NRC-6-038, 04/15/86 Status Panel (7.5.2.4)
31. Revision of FSAR: Complete 2NRC-6-066, 06/20/86 Cold Leg Accumulator Motor-Operated valve Position Indication (7.6.2.4)
32. Control System Failure Complete 2NRC-5-141, 10/15/85 Caused by Mal f unction 2NRC-6-054, 05/28/86 of Common Power Source or Instrument Line (7.7.2.3)
33. Confirmatory Site visit
a. Independence of Offsite Closed Power Circuits Between the Switchyard and Class 1E System (8.2.2.3)
b. Confirmatory of the Closed Protective Bypass (8.3.1.2)
c. Veri fication of DG Closed Start and Load Test (8.3.1.2)
d. DG Load Capability Closed Quali fication Test (8.3.1.9)

ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. ANO DATE (IF NOT ODMPLETE)

', e. Margin Qualification Closed Test (8.3.1.10) ,

f. Electrical Interconneo- Closed tion Between Redundant Class IE Buses (8.3.1.13)
g. Veri fication of Elec- Closed trical I ndepe ndence Between Power Supplies to Controls in Control Roan and Remote Loca-t ions (8.3.3.5) 34 Voltage Analysi s -- Open Approx. 6 Months veri ficaton of Test Prior To Fuel Results (8.3.1.1) Load an
35. Description and Analy- Open ,

sis of Conpliance with GDC 50 (8.3.3.7.1)

36. Co mpletion of Plant- Open 12/31/<86 Speci fic Core Damage Estimate Procedure Be fore Fuel Load (9.3.2.2) 37 Training Program for Open 12/86 the Operation and Melntenance of the Diesel Generators (9.5.4.1) 38 Vibration of instru- Open Fuel Load monts and Controls on Diesel Generators (9. 5.4.1 )

39 Surveillance of Lube Closed 2NRC-6-029, 03/26/86 011 Level in Diesel Generator Rocker Arm Lube Oil Reservoir (9.5.7)

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ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 40 Solid Weste Process Open 05/15/87 Control Program (11.4.2)

41. TMI Action Plan items
a. Ill.D.1.1 (13.5.2) Open 2NRC-6-080, 08/07/86 90 days prior to Fuel Loadi ng
b. II.K.1.5 and ll.K.1.10 Complete 2NRC-5-157, 12/24/85 (15.9.2; 15.9.3)
c. II.K.3.5 (15.9.9) Open 10/31/86
d. II.K.3.17 (15.9.11) Complete 2NRC-5-157, 12/24 /85
e. II.K.3.31 (15.9.14) Complete WC AP-10054 WCAP-10079 WCAP-11145 2NRC-6-069, 06/27/86
42. Plant-Speci fic Dropped Closed 2NRC-6-030, 04/01/86 Rod Analysis (15.4.3)
43. Steam Generator Tube Open SGTR-86-001, 02/28/86 Rupture (15.6.3) 44.- Quality Assurance Closed 2NRC-5-096, 06/28/85 Program (17.5) 24RC-5-152, 12/20/86
45. Cross-Training Program Complete 2NRC-6-073, 07/22/86
46. Control Room isolation Open 09/20/86 On High Radiation

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47. NRR Review of PGP for Complete NRR Action Only E0Ps (13.5.2) 48 Fire Protection: Amendment Open 01/87 12 revlow and site visit t
49. Steam generator high-level Complete 2NRC-6-087, 08/12/86 trip as non-protection system
50. Implementation letter of Open TBD ICCI System i
  • Hazards analysis is scheduled for completion at the end of 1986 and documented in early 1967 e' To be included in FSAR Amendment 13, December 1986 L

ATT/.CHMENT 3 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 16.0 TECHNICAL SPECIFICATIONS ITEM

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NO. ISSUE OLC STATUS LETTER NO. AND DATE REMARKS 1 Initial Draft Submit +al Cmplete 2NRC-4-144, 09/14/84 Awaiting E C Action

2. Pre-issue Revision 1 Complete 2NRC-5-153, 12/20/85 Awaiting EC Action
3. Response to Request for Complete 2NRC-6-044, 05/06/86 Awaiting E C Addl t lonal in fonnat ion Action 4 Informal meeting Complete Awalting E C wi th reviewer July,1986 Action i

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. ATTACt94ENT 4 REQUEST FOR ADDITIONAL INFORMATION RESPONSE DATE DATE_ SUBJECT DLC STATUS LETTER NO. AND DATE (lF NOT COWLETE) 03/03/86 Inadequate Core Cooling Closed 2NRC-6-037, 04/11/86 2NRC-6-075, 07/31/86 04/03/86 ATWS Complete 2NRC-6-% 3, 06/16/86 04/22/86 RCP Trip Criteria 10/31/86 05/23/86 Control Room Isolation 09/31/8 6 On High Radiation 06/27/86 ATWS 02/01/87 06/30/86 S.G. Level Control Complete 2NRC-6-087, 08/12/86 e

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ATTACHMENT 5 FSAR AMMENDMENTS AMCNDMENT TRANSMITTAL LETTER CERTIFICATION LETTER NUMBER NUMBER & DATE NUMBER & DATE 1 2NRC-3-028, 05/16/83 2NRC-3-031, 05/19/83 2 2NRC-3-043, 07/14/83 2NRC-3-050, 07/22/83 3 2NRC-3-077, 10/26/83 2NRC-3-085, 11/04/83 4 2NRC-3-096, 12/02/83 2NRC-3-100, 12/13/83 5 2NRC-4-011, 02/09/84 2NRC-4-025, 03/09/84 6 2NRC-4-048, 04/27/84 2NRC-4-054, 05/09/84 7 2NRC-4-098, 07/02/84 2NRC-4-103, 07/13/84 8 2NRC-4-154, 09/25/84 2NRC-4-161, 10/08/84 9 2NRC-4-210, 12/18/84 2NRC-4-213, 12/27/84 10 2NRC-5-075,05/20/85 2NRC-5-087, 06/07/8 5 11 2NRC-6-010, 01/28/86 2NRC-6-012, 02/04/86 12 2NRC-6-066, 06/20/86 2NRC-6-068, 06/27/86