ML20210B065

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Forwards Current Lists,As of 870122,re SER Outstanding Issues.Description of Issues Not Resolved to Staff Satisfaction Requested
ML20210B065
Person / Time
Site: Beaver Valley
Issue date: 01/30/1987
From: Carey J
DUQUESNE LIGHT CO.
To: Harold Denton, Tam P
Office of Nuclear Reactor Regulation
References
2NRC-7-019, 2NRC-7-19, NUDOCS 8702090067
Download: ML20210B065 (12)


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M 2NRC-7-019 Beaver Valley No. 2 Unit Project Organizatim Telecopy 412) 3 5200 Ext.160 S.E.G. Building P.o. Box 328 January 30, 1987 Shippingport, PA 15077 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Conmission Washington, DC 20555 ATTENTION: Mr. Peter Tam, Project Manager Divisiori 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 January 22, 1987 which provide our understanding of outstanding issues. Itens iaentified as "conplete" are those for which responses have been provided and no confinnation of status has yet Deen received fran the staff. We consider these itens satisfactorily closed unless notified otherwise. In order to pennit timely resolution of itens iden-tified as "conplete" which may not be resolved to the staff's satisfaction, please proviae a specific description of the issue which renains to be resolved. Iteus identified as "confinnatory" are based upon fonnal or informal conmunications or agreenents with the staff. Please inform us of any disagree-ment of status described on the attached list.

DUQUESNE LIGHT COMPANY By V J.L4. Carey v Senior Vice President RWR/ijr NR/ ISSUE / STATUS achments NAR cc: Mr. P. Tan, Project Manager - w/ attachments Mr. J. beall, NRC Sr. Resident Inspector - w/ attachments INPO Records Center - w/ attachments NRC Document Control Desk - w/ attachments 87020 PR y $80 PDR12 4 k\

ATTACHMENT 1 l SAFETY EVALUATION REPORT REVI EW STATUS TABLE 1.2 OPEN ISSUES ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 1 Prese rv ice /I nse rvice l Testing (3.9.6)

a. Preservice Testi ng Del eted 2NRC-5-154, 12/26/85 2NRC-6-034, 04/09/86
b. Inservice Testi ng Open TBD 2 Pump and Valve Leak Closed 2NRC-6-005, 01/09/86 Test i rg (3.9.6)
3. ICC Instrumentation Closed 2NRC-5-079, 05/31/8 5 (item i t.F.2 of NUREG 2NRC-6-037, 04/11/86 0737) (4.4.7) 4 Preserv ice /i nserv ice inspection Program (5.2.4.3; 5.4.2.2; 6.6)
a. Preservice Inspection Ope n 2NRC-6-154, 12/26/85
b. Inservice inspection Open 03/31/87 5 Safe and Alternate Compl ete 2NRC-7-003, 01/06/86 Snutdown (9.5.1)
6. Management and Organt- Open 2NRC-6-097, 09/18/86 zation (13.1) o i 7 Cross-Traini ng Program Closed Carey to R. M. Keller (13.2.1.2) Letter 06/13/85 8 Emergency Preparedness Co nf i rmatory 2NRC-5-077, 05/28/85 Plan (13.3.5) 2NRC-6-092, 08/22/86 9 Initial Test Program (14) 2 a. Remote Shutdown Test Cl osed 2NRC-5-110, 07/29/85 2NRC-6-066, 06/20/86
b. Test Acceptance Closed 2NRC-5-110, 07/29/85 Criteria C. NUREG 0737 Item 1.G.1 Cl osed 2NRC-5-110, 07/29/85 2NRC-6-066, 06/20/86
d. Relief and Dump Valve Closed 2NRC-5-110, 07/29/85 Capacity Tests 2NRC-6-045, 05/06/86
e. Test Classification Closed 2NRC-5-110, 07/29/85 Di sc repa nci es
f. Accumulator isolation Cl os ed 2NRC-5-110, 07/29/85 valve Test 2NHC-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

. Systen Test 2NRC-6-066, 06/20/86 2NRC-6-070, 06/27/86

h. Safety injection Pump Closed 2NRC-6-066, 06/20/86 Test i

1 Turbine Plant CCW Test Closed 2NRC-6-066, 06/20/86 j Sched ul e i

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[ 10 Control Room Design Complete

, 11 Safety Parameter. Open 2NRC-5-151, 12/20/85 12/17/87 Display Systen (18.2) 2NRC-6-055, 04/09/36 2NRC-6-064, 06/16/86 "

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  • Uncompleted surveys will be a licensing condition.

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ATTACHMENT 2 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 1.4 CONFIRMATORY ISSUES 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 Li nks (2.2.2) 2 Dif f erential Settlement Open 2NRC-6-l l l , 10/23/86 03/31/87 of Buried Pipes (2.5.4.3.3)

3. Internally Generated Open Missiles (Outside Con-tai nment) (3.5.1.1) 4 Internally Generated Open Missiles (Inside Corr ta i nment) (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 Drawlq) of Break Open Locations (3.6.2) 8 Results of Jet Impi nge- 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 ASME Code Camponents 2NRC-6-061, 06/06/86 (3.9.3.1) 11 Item I I.D.1 of NUREG Open 2NRC-5-157, 12/24/8 5 0737 (3.9.3.2) 12 Seismic and Dynamic Complete 2NRC-6-057, 06/04/8 6 Quali tication of 2NRC-6-076, 08/04/86 l Mechanical and Electrl- 2NRC-6-113, 10/ 27/86 l cal Equi pment (3.10.1) i i

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

13. Pump and Valve Oper- Complete 2NRC-6-057, 06/04/86 ebility Assurance 2NRC-6-076, 08/09/86 (3.10.2) 2NRC-6-113, 10/27/86 14 Environmental Quallfl- Complete 2NRC-6-053, 05/23/86 cation of Mechanical NRC Add i t, 11/18/86 and Electrical Equip- 2NRC-6-121, 12/03/86 ment (3.11)
15. Peak Pellet Design Closed 2NRC-5-132, 09/13/8 5 Basis (4.2.1) 16 Discrepancies in the Clos ed 2NRC-5-132, 09/13/8 5 FSAR (4.2.2) 17 Rod Bowi ng Analysis 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, 09/13/8 5 lapse Time (4.2.3.2121)
20. Use of the Square-Root- Closed 2NRC-4-209,12/18/84 of-t he-S um-o f-t h e-Squares Method for Seismic and LOCA Load Calculation (4.2.3.3141)
21. Analysis of Combined Open 2NRC-6-002, 01/03/86 Los s-of-Coola nt- Acci-dent and Seismic dLoads (4.2.3.3141) 22 Natural Circulation Open 2NRC-5-157, 12/24/85 03/23/87 Test ( 5.4.7.5)
23. Reactor Coolant Systen Closed 2NRC-5-157, 12/24/85 High Point Vents

( 5.4.12 )

24 Blowdown Mass and Complete NRR Action Only j

Enengy Release Analysis Methodology (6.2.1.1; 6.2.1.3; 6.2.1.4)

25. Contai nment Sump 50% Open 2NRC-5-157, 12/24/85 01/30/87 Blockage Assumption 2NRC-6-059, 06/06/86 (6.2.2) i l

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

26. Design Modification of Complete 2NRC-6-067, 06/23/86 I Automatic Reactor Trip Using Shunt Coll Trip At tachment (7.2.2.3) 27 Automatic Openi ng of Closed Ame nd . 10, 05/30/85 Service water System 2NRC-5-157,12/24/85 l Valves MOV 113C a nd 1130 (7.3.3.10) e-28 IE Bulleti r. 80-06 Con- Open 04/15/87 cerns (7.3.3.13) 29 NUREG 0737 ltem II.F.1, Closed 2NRC-4-210, 12/18/84 Accident Monitoring 2NRC-5-157, 12/24/85 instrumentation Post-t io rs (7.5.2.2) 30 eypass and i noperative Open 2NRC-6-058, 04/15/86 Status Panel (7.5.2.4)
31. Revision of FSAR: Closed 2NRC-6-066, 06/20/86

) Cold Leg Accumulator I Motor-Operated valve ,

Position indication (7.6.2.4) 32 Control System Failure Complete 2NRC-5-141, 10/15/8 5 Caused by Malf unction 2NRC-6-054, 05/28/86 ,

of Common Power Source or instrument Line d (7.7.2.3) i 1

! 33. Confirmatory Site visit i

a. Independence of Of f site Closed Power Circuits Between tne Switchyard and Class 1E System (8.2.2.3)
b. Confirmatory of the Closed Protective Bypass i

(8.3.1.2)

c. Verification of DG Closed i Start ard Load Test

' (8.3.1.2) 4

d. DG Load Capability Closed Quali fication Test (0.3.1.9) i i

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

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 i ndependence Between Power Supplies to Controls in Control ,

Room and Remote Loca-tions (8.3.3.5) 34 Vol tage A na l ys i s -- Open Before Fuel Load Verificaton of Test Results (8.3.1.1) 35 Description and Analy- Ope n sis of Compliance with 03/87 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 Traini rg Progran for Open 02/15/87 the Operation and Maintenance of the Diesel Generators (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 Oil 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 Waste Process Open 05/15/87 Control Program (11.4.2) 41 TMI Action Plan items

a. 111.0.1.1 (13.5.2) Open 2NRC-6-080, 08/07/86 90 days prior to Fuel Loadi ng
b. B l .K.1.5 a nd l i .K.1.10 Open 2NRC-5-157, 12/24/85 01/30/87 (15.9.2; 15.9.3)
c. Bl.K.3.5 (15.9.9) Ope n 01/31/87
d. Bl.K.3.17 (15.9.11) Open 2NRC-5-157, 12/24/85 01/30/87
e. it.K.3.31 (15.9.14) Cl os ed 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 Open SGTR-86-001, 02/28/86 TBD Rupture (15.6.5) 44 Quality Assurance Closed 2NRC-5-096, 06/28/8 5 Program (17.5) 2NRC-5-152, 12/20/86
45. Cross-Training Program Complete 2NRC-6-073, 07/22/86 40 Control Room isolation Complete 2NRC-6-108, 10/16/86 On High Radiation Signal 47 NRR Review of PGP for Open 03/31/87 EUPs (13.5.2) 48 Fire Protection: Amendment 12 review and site visit a) Amerdment 12 review Closed 2NRC-6-066, 06/20/86 b) Site visit Open 02/87 c) Safety related systun Canpl ete 2NRC-7-003, 01/06/87 fire barrier deviations 49 Steam generator high-level Complete 2NRC-6-087, 08/12/86 trip as nor> protection syst em 50 Implementation letter of Open T80 ICCI System 51 Superheated steam in valve Complete 2NRC-6-099, 9/20/8 6 house due to steamli ne break

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

52. Initial Testi ng
a. Accumulator isolation Ope n Prior to mode 3 Valves
b. 50V, P0 15 tests Cmpl ete 2NRC-7-004, 01/12/87
c. Plant Performance af ter Open FSAR Amendment 15 MSiv closure
d. Steen E traction System and Ope n FSAR Amendment 15 Process Computer e Hazards analysis is scheduled for completion at the end of 1986 and documented in early 1987

ATTACHMENT 3 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 16.0 TECHNICAL SPECIFICATIONS ITEM NO. ISSUE DLC STATUS LETTER NO. AND DATE REMARKS

1. Initial Draf t Submittal Complete 2NRC-4-144, 09/14/84
2. Pre-issue Revision 1 Complete 2NRC-5-153, 12/20/85
3. Response to Request for Complete 2NRC-6-044, 05/06/86 Additional Information 4 Informal meeting Complete with reviewer July,1986
5. Comments on NRC initial Complete 2NRC-6-120, 11/ 28/86 Awaiting NRC Draf t of BV-2 Tech Specs issue of " Proof and Review" copy of BV-2 Tech Specs

ATTACHMENT 4 REQUEST FOR ADDITIONAL INFORMATION DATE SUBJECT

_DLC STATUS RESPONSE DATE LETTER NO. AND DATE 03/03/86 (lF NOT COWLETE )

Inadequate Core Cooling Closed 2NRC-6-037, 04/11/8 6 2NRC-6-075, 07/31/86 04/03/86 ATWS Cmplete 2NRC-6-063, 06/16/86 04/22/86 R02 Trip Criterla 05/23/86 01/30/87 Control Room isolation Cmplete On High Radiation 2NRC-6-108, 10/16/8 6 06/27/86 ATWS 06/30/86 04/01/87 S.G. Level Control Complete 2NRC-6-087, 08/12/86 11/26/86 Inservice Testing Open TBD 12/05/86 Confirmatory Issue 47 Open 03/31/87 l

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ATTACHMENT 5 FSAR AMENDMENTS AMENDMENT TRANSMITTAL LETTER CERTIFICATION LETTER NUMBER NUM8ER & DATE NUMBER & DATE t 1 2NRC-3-028, 05/16/83 2NRC-3-031, 05/19/83 a

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2 2NRC-3-043, 07/14/83 2NRC-3-050, 07/22/83 8

3 2NRC-3-077, 10/26/83 2NRC-3-085, 11/04/83 4 2NRC-3-096, 12/02/83 2tRC-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, 05/09/8 4 a.

l 7 2NRC-4-098, 07/02/84 2NRC-4-103. 07/13/84 1

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, 01/23/86 2NRC-6-012, 02/04/86 12 2NRC-6-066, 06/20/86 2NRC-6-%8, 06/27/86 '\

I 13 2NRC-7-004, 01/12/87 2NRC-7-010, 01/16/8 7 i

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