ML20206D723

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Forward Current Lists,As of 870327,providing Util Understanding of SER Outstanding Issues.Specific Description of Issues Not Resolved to NRC Satisfaction,Requested
ML20206D723
Person / Time
Site: Beaver Valley
Issue date: 04/02/1987
From: Carey J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2NRC-7-061, 2NRC-7-61, NUDOCS 8704130405
Download: ML20206D723 (12)


Text

,e Tes 2NRC-7-061 Beaver Valley No. 2 Unit Project Organization Telecopy S E.G. Building ,

P.O. Box 328 April 2, 1987 Shippingport, PA 15077 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

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 March 27, 1987 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 itens satisf actorily closed unless notified otherwise, in order to permit timely resolution of itens iden-tified as " complete" which may not be resolved to the staff's satisfaction, please provide a specific description of the issue which renains to be r eso lved. Itens identified as " confirmatory" are based upon formal or informal communications or agreenents with the staff. Please inform us of any disagree-ments of status described on the attached list.

DUQUESNE LIGHT COMPANY By . _

K d.Wan ey (f Senior Vice President RWR/ijr NR/RWR/ISU/ STAT Attachments AR/NAR l

l cc: Mr. P. Tam, Project Manager - w/ attachments Mr. J. Beall, NRC Sr. Resident inspector - w/ attachments Ms. A. Asars, NRC Resident inspector - w/ attachments Dr. T. E. Murley, NRC Region 1 Administrator - w/ attachments INPO Records Center - w/ attachments l

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. . ATTACHMENT 1 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 1.2 OPEN ISSLES ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (lF NOT COMPLETE)-

1. Preservice/ Inservice Twsting (3.9.6)
a. Preservice Testing Del eted 2NRC-5-154, 12/26/85 2NRC-6-034, 04/09/86
b. Inservice Testing Open TBD 2 Pump and Valve Leak Closed 2NRC-6-005, 01/09/86 Testing (3.9.6)
3. ICC Instrumentation Closed 2NRC-5-079, 05/31/85

( l t en l l. F.2 o f NUR EG 2NRC-6-037, 04/11/86 0737) (4.4.7) 4 Preservice/ inservice inspection Program (5.2.4.3; 5.4.2.2; 6.6)

a. Preservice inspection Open 2NRC-6-154, 12/26/85
b. Inservice inspection Open 06/01/88
5. Safe and Alternate Complete 2NRC-7-003, 01/06/86 Shutdown (9.5.1)
6. Management and Organi- Complete 2NRC-6-097, 09/18/86 zation (13.1) 24RC-7-033, 03/02/87 7 Cross-Training Program Closed Carey to R. M. Keller (13.2.1.2) Letter 06/13/85
8. Emergency Preparedness Confirmatory 2NRC-5-077, 05/28/85 Plan (13.3.3) 24RC-6-092, 08/22/86 9 Initial Test Program (14)
a. Remote Shutdown Test Closed 2NRC-5-110, 07/29/8 5 2NRC-6-066, 06/20/86
b. Test Acceptance Closed 2NRC-5-110, 07/29/85 Criteria
c. NUREG 0737 Itan 1.G. I Cl osed 2NRC-5-l io, 07/29/85 2NRC-6-066, 06/20/86
d. Relief and Dump Valve Closed 2NRC-5-110, 07/29/8 5 Capacity Tests 2NRC-6-045, 05/06/86
e. Test Classification Cl os ed 2NRC-5-110, 07/29/85 Di sc repancies
t. Accumulator Isolation Cl osed 2NRC-5-110, 07/29/85 Valve Test 2NRC-6-066, 06/20/86

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ITEM RESPONSE DATE NO. ISSUE OLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE)

g. . Condenser Hotwell Level Closed 2NRC-5-110, 07/29/85 Systa Test 2NRC-6-066, 06/20/86 2NRC-6-070, 06/27/86
h. Safety injection Pump CIosed 2NRC-6-066, 06/20/86 Test I. Turbine Plant CCW Test Closed 2NRC-6-066, 06/20/86 Schedul e 10 Control Room Design Complete
  • Uncompleted surveys will be a licensing condition.
    • Resolution of open items by first refueling will be a licensing condition.

ATTAC W NT 2 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 1.4 CONFlRMATORY lSSUES ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE)

1. Operating Procedures Closed 2NRC-6-078, 08/04/86 for Continuous Communi- 2NRC-6-091, 08/19/86 cation Links (2.2.2)
2. Differential Settlement Complete 2NRC-6-111, 10/23/86 of Buried Pipes 2NRC-7-045, 03/09/87

( 2. 5.4.3. 3)

3. Internally Generated Open 04/01/87 Mi ssiles (Outside Cona tainment) (3.5.1.1) 4 Internally Generated Open 04/01/87 Mi ssiles (Inside Con-tainment) (3.5.1.2)
5. Turbine Missiles Open 2NRC-5-157, 12/24/85 04/15/87 (3.5.1.3) 2NRC-7-033, 03/02/87 6 Analysis of Pipe Break Open 04/01/87 Protection Outside Con- ,

i tainment (3.6.1) 7 FSAR Drawing of Break Open 04/01/87 Locations (3.6.2) 8 Results of Jet Impinge- Open 04/01/87

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ment Et fects (3.6.2)

I 9 Soil 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 Components 2NRC-6-061, 06/06/86

! (3.9.3.1) l I

11. Item 11.0.1 of NUREG Open 2NRC-5-157, 12/24/85 04/03/87 0737 (3.9.3.2)
12. Seismic and Dynamic Complete 2NRC-6-057, %/04/86 QualI fIcation of 2NRC-6-076, 08/04/86 Mechanical and Electri- 2NRC-6-113, 10/27/86 cal Equipment (3.10.1) l , , - - - - , . ,- .-- --

. ITEM RESPONSE DATE NO . - ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE 1 13 Pump and Valve Oper- Complete 2NRC-6-057, 06/04/86 ability Assurance 2NRC-6-076, 08/09/86 (3.10.2) 2NRC-6-113, 10/27/86 14 Environmental Qualifi- Complete 2NRC-6-053, 05/23/86 cation of Mechanical PRC Audit, 11/18/86 and Electrical Equip- 2NRC-6-121, 12/03/86 ment (3.11) 2NRC-6-036, 03/04/87 15 Peak Pellet Design Closed 2NRC-5-132, 09/13/85 Ba si s ( 4.2.1 )

16 Discrepancies in the Closed 2NRC-5-132, 09/13/85 FSAR (4.2.2) 17 Rod Bowing Analysis Closed 2NRC-4-102, 07/12/84 (4.2.3.11611 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, 09/13/8 5 lapse Time (4.2.3.2121) 20 Use of the Square-Root- Closed 2NRC-4-209,12/18/84 of-the-Sum-of-the-Squares Method for Seismic and LOCA Load Calcuiation (4.2.3.3141) 21 Analysis of Combined Complete 2NRC-6-002, 01/03/86 Los s-of-Coola nt- Acci-

! dont and Seismic dLoads l (4.2.3.3141)

I I 22 Natural Circulation Open 2NRC-5-157, 12/24/85 Af ter Fuel Test ( 5.4.7.5) Load

23. Reactor Coolant System Closed 2NRC-5-157, 12/24/85 High Point Vents (5.4.12) l 24 Blowdown Mass and Complete NRR Action Only Energy 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 03/27/87 Blockage Assumption 2NRC-6-059, 06/06/86 (6.2.2)

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. 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, 05/30/8 5 Service Water Systen 2NRC-5-157, 12/24/85 valves MOV 113C ond 113D (7.3.3.10)

28. IE Bulletin 80-06 Con- Open 04/15/87 corns (7.3.3.13)
29. NUREG 0737 Item II.F.1, Closed 2NRC-4-210, 12/18 /84 Accident Monitoring 2NRC-5-157, 12/24/85 instrumentation Posl-tions (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: Closed 2NRC-6-066, 06/20/86 Cold Leg Accumulator Motor-Operated valve Position Indication (7.6.2.4)
32. Control System Failure Open 2NRC-5-141, 10/15/85 03/27/87 Caused by Malf 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 Ottsite Closed Power Circuits Between the Switchyard and Class 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 Qualification Test (8.3.1.9)

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

e. Mergin Qualification Closed Test (8.3.1.10)
t. Electrical Interconnec- Closed tion Between Redundant Class 1E Buses (8.3.1.13)
g. Verification of Elec- Closeo tr ical I ndependence Between Power Supplies to Controls in Control
Roan and Remote Loca-t ions (8.3.3.5) 34 Voltage Analysi s -- Open 3/27/87 Verificaton of Test Results (8.3.1.1)
35. Description and Analy- Open 04/01/87 sis of Compilance with GDC 50 (8.3.3.7.1) 36 Completion of Plant- Open Before Fuel Load Speci fic Core Damage Estimate Procedure Before Fuel Load (9.3.2.2)
37. Training Progran for Open 04/15/87 the Operation and Maintenance of the l

i Diesel Generators l (9.5.4.1)

38. Vibration of instru- Open Fuel Load ments 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 l

Lube Oil Reservoir (9.5.7)

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

40. Solid Waste Process Open 05/15/87 Control Program (11.4.2)
41. TMI Action Plan items
a. lil.D.1.1 (13.5.2) Open 2NRC-6-080, 08/07/86 04/15/87
b. II.K.l.5 and ll.K.1.10 Open 2NRC-5-157, 12/24/85 04/15/87 (15.9.2; 15.9.3)
c. I I . K.3.5 ( 15.9.9 ) Open 04/15/87
d. il.K.3.17 (15.9.11) Open 2NRC-5-157, 12/24/85 04/15/87
e. I I.K.3.31 ( 15.9.14) Cl osed WCAP-10054 WCAP-10079 WCAP-11145 2NRC-6-069, 06/27/86 42 Plant-Specific Dropped Closed 2NRC-6-030, 04/01/86 Rod Analysis (15.4.3)
43. Steam Generator Tube Complete SGTR-86-001, 02/28/86 Rupture (15.6.3) 44 Quality Assurance Closed 2NRC-5-096, 06/28/8 5 Program (17.5) 24RC-5-152, 12/20/86
45. Cross-Training Program Complete 2NRC-6-073, 07/22/86
46. Control Room isoletion Complete 2NRC-6-108, 10/16/86 On High Radiation 2NRC-7-044, 03/09/87 Signal 47 NRR Review of PGP for Open 03/28/87 E0Ps (13.5.2)
48. Fire Protection: Amendment 12 review and site visit a) Amendment 12 review Cl osed 2NRC-6-066, 06/20/86 b) Site visit Complete 2NRC-7-026, 02/11/87 2NRC-7-040, 03/05/87 c) Safety related system Complete 2NRC-7-003, 01/06/87 fire barrier deviations
49. Steam generator high-level Complete 2NRC-6-087, 08/12/86 trip as non-protection 2NRC-6-039, 03/04/87 system
50. Implementation letter of Open TBD ICCI System
51. Superheateu stean in valve Complete 2NRC-6-099, 9/20/86 house due to steamline 34RC-6-126, 12/19/87 break 2NRC-7-056, 03/24/87

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

-52. Initial Testing

a. Accumulator isolation Open Prior to mode 3 Valves
b. SOV, PO IS tests Copl ete 2NRC-7-004, 01/12/87
c. Plant Performance after Complete 2NRC-7-033, 03/02/87 MSly close e

- d. Steen Extrac?lon Systun and Ca plete 2NRC-7-033, 03/02/87 4

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ATTAC*ENT 3 SAFETY EVALUATION REPORT REVIEW STATUS TABLE- 16.0 TECHNICAL SPEClFICATIONS ITEM NO. ISSUE DLC STATUS LETTER NO. AND DATE REMARKS i

1. Initial Draft Submittal Complete 2NRC-4-144, 09/14/84 i
2. Pre-issue Revision 1 Complete 2NRC-5-153, 12/20/85
3. Response to Request for Complete 2NRC-6-044, 05/06/86 Addi tional Information 4 Informal meeting Complete wi th rwiewer July,1986 5.' Comments on NRC Initial Complete 2NRC-6-120, 11/28/86 Awaiting E C Drett of BV-2 Tech Specs issue of "Proot and Review" copy of BV-2 Tech Specs i

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ATTACHMENT 4 REQUEST FOR ADDITIONAL INFORMATION RESPONSE DATE DATE SUBJECT DLC STATUS. LETTER NO. AND DATE (IF NOT COMPLETE) 03/03/86 Inacequate Core Cooling Closed 2NRC-6-037, 04/11/86 2NRC-6-075, 07/31/86 04/03/86 ATWS Closed 2NRC-6-063, 06/16/86 04/22/86 RCP Trip Criteria 04/15/87 05/23/86 Control Room Isolation Complete 2NRC-6-108, 10/16/86 On High Radiation 2NRC-7-044, 03/09/87 06/27/86 ATWS 04/01/87 06/30/86 S.G. Level Control Complete 2NRC-6-087, 08/12/86 11/26/86 Inservice Testing Open TBD 13/03/86 Confirmatory issue 47 Open 03/27/87 02/27/87 Confi rmatory issue 32 Open 03/27/87 03/05/87 Confi rmatory issue 14 Complete 2NRC-7-036, 03/04/87 03/11/87 initial Test Program Open 03/27/87 i

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ATTACHMENT 5 FSAR AMEN 04ENTS AMENDMENT 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 13 2NRC-7-004, 01/12/87 2NRC-7-010, 01/16/87 14- 2NRC-7-014, 01/30/87 2NRC-7-022, 02/04/87 15 2NRC-7-033, 03/02/87 2NRC-7-037, 03/04/87 l

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