ML20204H631

Forwards List of Status of SER Outstanding Issues.Requests NRC Identify Issues Which Remain Unresolved

ML20204H631
Person / Time
Site:	Beaver Valley
Issue date:	08/04/1986
From:	Carey J DUQUESNE LIGHT CO.
To:	Harold Denton, Tam P Office of Nuclear Reactor Regulation
References
2NRC-6-078, 2NRC-6-78, NUDOCS 8608080167
Download: ML20204H631 (11)

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'Af DuquesneUsht seaver Valley No. 2 Unit Project Organization 2NRC-6-078 h 2l Shippingport. PA 15077 (412) 643-5200

'# I" Ngf2t August 4, 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 five current lists, as of July 22, 1986, which provide our understanding of outstanding issues. Items identified as "canplete" are those for which responses have been provided and no confirmation of status has yet been received fran the staff. We consider these itens satisfactorily closed unless notified otherwise. In order to permit timely resolution of itens identified as "canplete" which may not be resolved to the staff's satisfaction, please provide a specific description of the issue which renains to be resolved. Items identified as " confirmatory" are based upon formal or informal conmunications or agreenents with the staff.

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

DUQUESNE LIGHT COMPANY 1

By f V. # Carey Vice President RWR/ijr NR/ ISSUE / STATUS Attachments

@/NAR cc: Mr. W. Troskoski, Senior Resident Inspector - w/ attachments Mr. L. Prividy, Resident Inspector - w/ attachments DI 0608080167 860004 Il

{DR ADOCK 05000412 PDR

ATTACHMENT 1 SAFETY EVALUATION REPORT R EV I EW STATUS TABLE 1.2 OPEN ISSUES j ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 1 I 1 Preservice/ Inservice Complete 2NRC-5-154, 12/26/85 Testing (3.9.6) 34RC-6-034, 04/09/86 2 Pump and Valve Leak Complete 2NRC-6-005, 01/09/86 4

Testing (3.9.6)

3. ICC Instrumentation Complete 2NRC-5-079, 05/31/8 5 (Iten ll.F.2 of NUREG 2NRC-6-037, 04/11/86 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 08/86 j Shutdown (9.5.1) i

! 6 Management and Organi- Open 09/8 6 zation (13.1)

7. Cross-Training Program Confirmatory Cerey to R. M. Keller (13.2.1.2) 45 Letter 06/13/85 8 Emergency Preparedness Open 2NRC-5-077, 05/28/85 07/86 Plan (13.3.3) 9 Initial Test Program (14) 1 a. Remote Shutdown Test Complete 2NRC-5-110, 07/29/85 1 2NRC-6-066, 06/20/86

b. Test Acceptance Closed 2NRC-5-110, 07/29/85 Criteria i

c. NUREG 0737 Item 1.G.1 Complete 2NRC-5-l lo, 07/29/8 5 2NRC-6-066, 06/20/86

d. Rollet and Dump Valve Compl ete 2NRC-5-llo, 07/29/85 Capacity Tests 2NRC-6-045, 05/06/86 a e. Test Classification Closed 2NRC-5-110, 07/29/85 Di screpancles

f. Accumulator Isolation Complete 2NRC-5-110, 07/29/85 4 Valve Test 2HRC-6-066, 06/20/86 i

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

< g. Condenser Hotweli Level Complete 2NRC-5-110, 07/29/85 Systen Test 2NRC-6-066, 06/20/86 1 2NRC-6-070, 06/27/86

! h. Safety injection Pump Complete 2NRC-066, 06/20/86

, Test i

1. Turbine Plant CCW Test Complete 2NRC-066, 06/20/86 Schedule 10 Control Room Design Open 2NRC-5-147, 12/02/85 01/87 Rev i ew ( 18.1) 11 Safety Parameter Complete 2NRC-5-151, 12/20/8 5 Di splay Systen (18.2) 2hRC-6-033, 04/09/86 2tRC-6-064, 06/16/86 A

ATTACHMENT 2 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 1.4 CONFlf94ATORY ISSUES ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 1 Operating Procedures Open 07/31/86**

for Continuous Communi-cation Links (2.2.2) 7, Olf ferential Settlement Open 10/31/86 of Bur ied Pipes (2.5.4.3.3) l l 3. Internally Generated Open 2

Missiles (Outside Con-l tainment) (3.5.1.1) 4 Internally Generated Open I Missil es (Inside Con-tainment) (3.5.1.2)

, 5. Turbine Missiles Open 2NRC-5-157, 12/24/85 01/30/87 (3.5.1.3) f

6. Analysis of Pipe Break Open Protection Outside Con-ll tainment (3.6.1) j 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, 08/07/8 5 action Analysis (3.7.3)

10. Design Documentation of Complete 2NRC-6-001, 01/03/86 l

ASME Code Components 2NRC-6-061, 06/06/86

{ (3.9.3.1)

11. Item II.D.1 of NUREG Complete 2NRC-5-157, 12/24 /8 5 0737 (3.9.3.2)

12. Sel smic and Dynamic Open 2NRC-6-057, 6/4/86 09/15/86 Quali fication of Mechanical and Electri-I cal Equi pment (3.10.1) 4

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

13. Pump and Valve Oper- Open 2NRC-6-057, 06/04/86 09/15/86 ability Assurance (3.10.2) 14 Environmental Quallfl- Open 2NRC-6-053, 05/23/86 09/30/86 cation of Mechanical and Electrical Equip-l ment (3.11)

15. Peak Pellet Design Closed 2NRC-5-132, 09/13/85 Ba si s ( 4.2.1) j 16. Discrepancies in the Closed 2NRC-5-132, 09/13/8 5 FSAR (4.2.2) 17 Rod Bowing Analysis Closed 2NRC-4-102, 07/12/84 (4.2.3.1161) ,

4 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 I

of-t he-Sum-o f-t h e-Squares Method for SeIsmlc and LOCA Load Calculation (4.2.3.3141)

21. Analysis of Combined Complete 2NRC-6-002, 01/03/86 Los s-of-Coola n t-Accl-dont and Seismic dLoads (4.2.3.3141) f j 22. Natural Circulation Open 2NRC-5-157, 12/24/85 12/31/86 j Test (5.4.7.5) l 23. Reactor Coolant System Open 2NRC-5-157, 12/24/85 12/31/86 High Point vents (5.4.12) 1 24 Blowdown Mass and Complete NRR Action Only i Energy Release Analysis Methodology (6.2.1.1; i 6.2.1.3; 6.2.1.4) l 25 Containment Sump 501 Complete 2NRC-5-157, 12/24 /8 5

! Blockage Assumption 2NRC-6-059, 06/06/86 (6.2.2)

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t 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 Shur.t Coll Trip Attachment (7.2.2.3) 27 Automatic Opening of Closed Amend. 10, 05/30/8 5 i

Service Water Systen 2NRC-5-157, 12/24/85 Valves MOV 113C and 113] (7.3.3.10) i 28 IE Bulletin 80-06 Con- Open 12/31/86

carna ( 7.3.3.13) l 29 NUREG 0737 Item l i.F.1, Closed 2NRC-4-210, 12/18/84 Accident Monitoring 2NRC-5-157, 12/24/85 Instrumentation Posi-tions (7.5.2.2) 30 Bypass and inoperative Complete 2NRC-6-038, 04/15/86 Status Panel (7.5.2.4) 2

31. Revision of FSAR: Complcte 2NRC-6-066, 06/20/86 Cold Log Accumulator Motor-Operated Valve 4

Position Indication (7.6.2.4) l 32. Control System Failure Complete 2NRC-5-141, 10/15/85 i Caused by MeIf unctlon 2NRC-6-054, 05/28/86 of Common Power Sour:e

! 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. Verification of DG Closed Start and Load Test (8.3.1.2)

d. DG Load Capability Closed Quali fication Test (8.3.1.9) i

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

e. Mergin Qualification Closed

! Test (8.3.1.10)

I f. Electrical Interconnec- Closed j tion Between Redundant Class IE Buses

] (8.3.1.13) i g. Verification of Elec- Closed l trical independence l Between Power Supplies i to Contrcis !n Centro!

Room and Remote Loco-l t ions (6.3.3.5) t 34 Voltago Analysis -- Open Approx. 6 Months Verificaton of Test Prior To Fuel Results (8.3.1.1) Load

(

Description and Analy- Open een i 35.

sls of Conpliance witn i GDC 50 (8.3.3.7.1)

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36. Completion of Plant- Open 12/31/86 Specific Core Damage Estimate Procedure Before Fuel Load (9.3.2.2)

37 Training Program for Open 12/8 6 I

the Operation and Maintenance of the i Diesel Generators f (9.5.4.1) i

38. Vibration of instru- Open Fuel Load ments and Controls on Diesel Generators (9.5.4.1) t 39 Surveillance of Lube Complete 2NRC-6-029, 03/26/8 6 i Oil Level in Diesel f Generator Rocker Arm

! Lube Oil Reservoir l (9.5.7) 4

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ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 40 Solid Weste Process Open 12/31/86 Control Program (11.4.2) 41 TMI Action Plan items

a. 111.D.1.1 (13.5.2) Open 90 days prior to Fuel Loading

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) Complete No Action Required

d. II.K.3.17 (15.9.11) Complete 2NRC-5-157, 12/24/8 5

e. II.K.3.31 (15.9.14) Cumplete WCAP-10054 WCAP-10079 WC AP-11145 2NRC-6-069, 06/27/86

42. Plant-Specific Dropped Complete 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 Quali ty 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 l

46 Control Room isolation Open 08/15/86 On High Radiation Signal 47 NRR Review of PGP for Complete NRR Action Only E0Ps (13.5.2)

• Hazards analysis is scheduled for completion at the end of 1986 and documented in early 1987.

8' Procedure EPP/IP 7.3, which will be submitted as part of open issue No. 8, requires that the Director, Emergency Services, Beaver County Emergency Management Agency be contacted to provide information regarding new sources of toxic materials which could require control room isolation, een To be included in FSAR Amendment 13, December 1986

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 Amalting NRC Action 2 Pre-issue Revision 1 Complete 2NRC-5-153, 12/20/85 Awalting NRC Act ion

3. Response to Request for Complete 2NRC-6-044, 05/06/86 Awalting NRC Addi tional In format ion Act ion

ATTAC M NT 4 REQUEST FOR ADDITIONAL INFORMATION RESPONSE DATE DATE SUBJECT DLC STATUS LETTER NO. AND DATE (IF NOT CO W LETE) 03/03/86 inadequate Core Cooling Complete 2NRC-6-037, 04/11/86 04/03/86 ATWS Cooplete 2NRC-6-063, 06/16/86 04/22/86 RO' Trip Criteria 08/29/8 6 05/23/86 Control Room isolation 08/15/86 On High Radiation j 06/27/86 ATwS 09/15/86 i

06/30/86 S.G. Level Control 09/15/86 I

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! ATTACENT 5 FSAR AMMENDMENTS 1

l AMENDMENT TRANSMITTAL LETTER CERTIFICATION LETTER NUMtlER NUMt3ER & DATE NUteER & DATE

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1 2NRC-3-028, 05/16/83 2NRC-3-031, 05/19/83

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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, 12/02/85 2NRC-3-100, 12/13/8 3 [

5 2NRC-4-Oll, 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 i

9 2NRC-4-210, 12/18/84 2NRC-4-213, 12/27/84 1

10 2NRC-5-075, 05/20/85 2NRC-5-087, 06/07/85 1

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 i

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