ML20138B423

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Forwards Lists of SER Outstanding Issues,Providing Util Understanding as of 860315.Specific Description of Issues Remaining to Be Resolved Requested
ML20138B423
Person / Time
Site: Beaver Valley
Issue date: 03/20/1986
From: Carey J
DUQUESNE LIGHT CO.
To: Harold Denton, Tam P
Office of Nuclear Reactor Regulation
References
2NRC-6-028, 2NRC-6-28, NUDOCS 8603250057
Download: ML20138B423 (9)


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$t$u'g"[8l'is*/$s*""*'**'**" March 20, 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 Gentl emen :

Attached are three current lists, as of March 15, 1986, which pro-vide our understanding of outstanding issues. Items identified as "com-plete" are those for which responses have been provided and r.o 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 communications or agreements with the staff.

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

DUQUESNE LIGHT COMPANY By V.ice J/ President Carey /

TRS /sms NR/SER/ LETTER Attachments cc: Mr. W. Troskoski, Resident Inspector (w/ attachments)

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

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ATTACHMENT 1 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 1.2 OPEN ISS LES ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE)

1. Preservice/ Inservice Testing (3.9.6) Open 2NRC-5-154,12/26/85 04/86
2. Pump an Valve Leak Testing (3.9.6) Complete 2NRC-6-005, 01/09/86
3. ICC Instrumentation (Item II.F.2 of NUREG 0737)(4.4.7) Open 2NRC-5-079, 05/31/85 04/86
4. Preservice/ Inservice Inspection Program (5.2.4.3; 5.4.2.2; 6.6) Open 2NRC-5-154,12/26/85 12/31/86
5. Safe and Alternate S hutdown (9.5.1 ) Open 08/86
6. Management and Organi-zation (13.1) Open TBD
7. Cross-Training Program Carey to R. M. Keller (13.2.1.2) Complete Letter 06/13/85
8. Emergency Preparedness Plan (13.3.3) Open 2NRC-5-077,05/28/85 07/86
  • NRR Review of PGP for E0Ps (13.5.2) Complete NRR Action Only
9. Initial Test Program (14)
a. Remote Shutdown Test Complete 2NRC-5-110, 07/29/85
b. Test Acceptance Criteria Closed 2NRC-5-110, 07/29/85
c. HUREG 0737 Item I.G.1 Open 2NRC-5-110, 07/29/85 07/86
d. Relief and Dump Valve Capacity Tests Open 2NRC-5-110, 07/29/85 04/86
e. Test Classification Discrepancies Open 2NRC-5-110, 07/29/85 07/86
f. Accumulator Isolation Valve Test Complete 2NRC-5-110, 07/29/85
g. Condenser Hotwell Level System Test Complete 2NRC-5-110, 07/29/85

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

h. Safety Injection Pump Test Open 07/86
i. Turbine Plant CCW Test Schedul e Open ,

07/86

10. Contol Room Design Review (18.1) Open 2NRC-5-147,12/02/85 01/87
11. Safety Parameter Display System (18.2) Open 2NRC-5-151,12/20/85 03/25/86
  • Item was found in text but not in Table 1.2.

TBD To be determined.

ATTACHMENT 2 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 1.4 CONFIRMATORY ISSLES ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE)

1. Operating Procedures for Continuous Communi-cation Links (2.2.2) Open 06/30/86
2. Differential Settlement of Buried Pipes (2.5.4.3.3) Open 06/30/86
3. Internally Generated Missiles (Outside Con- ,

tainment) (3.5.1.1 ) Open ,

4. Internally Generated Missiler (Inside Con-
  • tainment) (3.5.1.2) Open
5. Turbine Missiles (3.5.1.3) Open 2NRC-5-157, 12/24/85 01/30/87
6. Analysis of Pipe Break Protection Outside Con-tainment (3.6.1) Open
7. FSAR Drawing of Break Locat ions (3.6.2) Open
8. Results of Jet Impinge-ment Effects (3.6.2) Open
9. Soil Structure Inter-action Analysis (3.7.3) Complete 2NRC-5-ll4, 08/07/85
10. Design Documentation of ASME Code Components

( 3.9.3.1 ) Compl ete 2NRC-6-001, 01/03/86

11. Item II.D.1 of NUREG i 0737 (3.9.3.2) Complete 2NRC-5-157, 12/24/85 I
12. Seismic and Dynamic Qualification of Mechanical and Electri- I cal Equipment (3.10.1) Open 07/30/86
ITEM RESPONSE DATE j N0. _ ISSUE DLC ST_ATUS LETTER NO. AND DATE (IF NOT COMPLETE) i Pump and Valve Oper-13.

ability Assurance

} ( 3.10.2) Open 07/30/86

14. Environmental Qualifi-cation of Mechanical and Electrical Equip-ment (3.11) Open 07/30/86
15. Peak Pellet Design Basis (4.2.1) Complete 2NRC-5-132, 09/13/85 l

l 16. Discrepancies in the FS AR (4.2.2) Complete 2NRC-5-132, 09/13/85

17. Rod Bowing Analysis (4.2.3.1[6]) Complete 2NRC-4-102, 07/12/84 i 18. Fuel Rod Internal Pres-sure (4.2.3.1[8]) Complete 2NRC-5-132, 09/13/85 Predicted Cladding Col-19.

lapseTime(4.2.3.2[2]) Complete 2NRC-5-132, 09/13/85

20. Use of the Square-Root-of-t he-S um-of-t he-l Squares Method for Seismic and LOCA Load Calculation (4.2.3.3[4]) Complete 2NRC-4-209,12/18/84 21 . Analysis of Combined i Lo ss-of-Cool ant-Acc i-i dent and Seismic Loads j (4.2.3.3[4]) Complete 2NRC-5-002, 01/03/86
22. Natural Circulation 2NRC-5-157,12/24/85 Test (5.4.7.5) Complete NRR Action Only
23. Reactor Coolant System I High Point Vents

! ( 5.4.12) Complete 2NRC-5-157,12/24/85

24. Blowdown Mass and Energy Release Analysis I Methodology (6.2.1.1; 6.2.1.3; 6.2.1.4) Complete NRR Action Only
25. Containment Sump 50%

. Blockage Assumption (6.2.2) Open 2NRC-5-157, 12/24/85 04/30/86

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i l

i 1

ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER N0. AND DATE (IF NOT COMPLETE)

26. Design Modification of Automatic Reactor Trip Using Shunt Coil Trip Attachment (7.2.2.3) Open 06/31/86
27. Automatic Opening of Service Water System Valves MOV ll3C and Amend. 10, 05/30/85 1130 (7.3.3.10) Complete 2NRC-5-157,12/24/85
28. IE Bulletin 80-06 Con-cerns (7.3.3.13) Compl ete NRC Action Only
29. NUREG 0737 Item II.F.1, Accident Monitoring Instrumentation Posi- 2NRC-4-210,12/18/84 tions (7.5.2.2) Complete 2NRC-5-157,12/24/85
30. Bypass and Inoperative Status Panel (7.5.2.4) Compl ete NRC Action Only 31 . Revision of the FSAR:

Cold Leg Accumulator Motor-Operated Valve Position Indication (7.6.2.4) Open 07/31/86

32. Control System Failure Caused by Malfunction of Common Power Source or Instrument Line (7.7.2.3) Open 2NRC-5-141,10/15/85 04/15/86
33. Confirmatory Site Visit
a. Independence of Offsite Power Circuits Between the Switchyard and Class lE System (8.2.2.3)
b. Confirmatory of the Protective Bypass

( 8.3.1.2)

c. Verification of DG Start and Load Tests (8.3.1.8)
d. DG Load Capability Qualification Test (8.3.1.9)
e. Margin Qualification Test (8.3.1.10)

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

f. Electrical Interconnec-tion Between Redundant Class lE Buses (8.3.1.13)
g. Verification of Elec-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 -- Aprox 6 Mths Verification of Test Prior to Fuel Resul t s (8.3.1.1 ) .Open Load
35. Description and Analy-sis of Compliance with GDC 50 (8.3.3.7.1) Open 07/31/86
36. Completion of Plant-Specific Core Damage Estimate Procedure Before Fuel Load (9.3.2.2) Open 12/31/86
37. Training Program for the Operation and Maintenance of the Diesel Generators

( 9. 5.4.1 ) Open 12/86

38. Vibration of Instru-ments and Controls on Diesel Generators

( 9.5.4.1 ) Open TBD

39. Surveillance of Lube Oil Level in Diesel Generator Rocker Arm Lube Oil Reservoir (9.5.7) Open 04/86
40. Solid Waste Process Control Program (11.4.2) Open 09/30/86

ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER N0. AND DATE (IF NOT COMPLETE) 41 . TMI Action Plan Items

a. III.D.l .1 (13.5.2) Open TBD
b. II.K.l.5 and II.K.l.10 (15.9.2; 15.9.3) Complete 2NRC-5-157,12/24/85
c. II.K.3.5 (15.9.9) Complete No Action Required
d. II .K.3.17 (15.9.11 ) Complete 2NRC-5-157,12/24/85
e. II.K.3.31 (15.9.14) Complete WCAP-10054 WCAP-10079
42. Plant-Specific Dropped Rod Analysis (15.4.3) Open 05/01/86 .
43. Steam Generator Tube Rupture (15.6.3) Open SGTR-86-001, 02/28/86
44. Quality Assurance Pro- 2NRC-5-096, 06/28/85 gram (17.5) Closed 2NRC-5-152,12/20/85
  • 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.
      • The confirmatory site visit was held 2/12-13/86. DLC is awaiting confirmation of the status of these items in the SER Supplement.

TBD To be determined. ,

I

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

1. Initial Draft Submittal Complete 2NRC-4-144, 09/14/84 Awaiting NRC Action
2. Pre-Issue Revision 1 Complete 2NRC-5-153,12/20/85 Awaiting NRC Action