ML20213G829

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Forwards Five Current Lists Providing Util Understanding of SER Outstanding Issues.Items Identified as Complete Considered Satisfactorily Closed.Specific Description of Issues Remaining Requested
ML20213G829
Person / Time
Site: Beaver Valley
Issue date: 05/11/1987
From: Carey J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
2NRC-7-113, NUDOCS 8705180472
Download: ML20213G829 (12)


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M 2NRC-7-ll3 (412)393-7546 Beaver Valley No. 2 Unit Project Organization Telecopy(412)393 7889 eu spgo gpg May 11, 1987 shippingport. PA 15077 -

United States Nuclear Regulatory Comission 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 May 11, 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 items satisfactorily closed unless notified otherwise. In order to permit timely resolution of items iden-tified 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 disagree-ments of status described on the attached list.

DUQUESNE LIGHT COMPANY By y

Senior4(J./Carey /

ice President RWR/ijr NR/RWR/ISU/ STAT Attachments AR/NAR 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 Mr. William T. Pussel, NRC Region I Administrator - w/ attachments INP0 Records Center - w/ attachments 8705180472 870511 A#p\

PDR ADOCK 05000412 E PDR f

ATTACHMENT 1 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 1.2 OPEN ISSUES ITEM RESPONSE D ATE NO. I SSUE DLC STATUS LETTER NO. AND DATE (I F NOT COMPLETE) 1 Preservice/ I n se rvi ce Testing (3.9.6) -

a.1Preservice Testing Deleted 2NRC 154, 12/26/85 2 PRC-6-034, 04/09/86

b. Inservice Testing Complete 2 NRC-7-084, 04/15/87
2. Pump and Valve Leak Closed 2 NRC-6-005, 01/09/86 Testing (3.9.6)
3. ICC Instrumentation Closed 2 NRC-5-079, 05/31/85 (item II .F.2 of NUREG 2NRC-6-037, 04/11/86 0737) (4.4.7) 4.- Preservico/ i n se rv Ice Inspection Program (5.2.4.3; 5.4.2.2; 6.6)
a. Preservice inspection Open 2NRC 154, 12/26/85
b. Inservice Inspection O pen 2 NRC-7-076, 04/13/87 06/01/88
5. Safe and Alternate Complete 2 NRC-7-003, 01/06/86 Shutdown (9.5.1) 6.' Management and Organi- Comp lete 2NRC-6-097, 09/18/86 zation (13.1) 2NRC-7-033, 03/02/87 7 Cross-Training Program Closed Carey to R. M. Kel ler (13.2.1.2) Lette r 06/13/85 8 Emergency Preparedness Con fi rma tory 2 NRC-5-077, 05/ 28/85 Plan (13.3.3) 2NRC-6-092, 08/22/86 9 Initial Test Program (14)

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a. Remote Shutdown Test Closed 2NRC-5-110, 07/29/85 2NRC-6-066, 06/20/86
b. Test Acceptance Closed 2 NRC-5-110, 07/29/85 l.

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c. NUREG 0737 Item I .G.1 Closed 2MRC 110, 07/29/85 2 NRC-6-066, 06/20/86
d. Rollef and Dump Valve Closed 2NRC-5-110, 07/29/85 i Capacity Tests 2NRC-6-045, 05/06/86
e. Test Classi fication Closed 2 NRC-5-I l0, 07/29/85 Discrepancies i f. Accumulator i solation Clo sed 2NRC-5-110, 07/29/85 Valve Test 2*RC-6-066, 06/20/86 i

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4 TEM RESPONSE DATE -

NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COWLETE)

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g. . Condenser Hotwell Level Closed 2NRC-5-110, 07/29/85 System Test 2mC-6-066, 06/20/86 2mC-6-070, 06/27/86 -

~ h.- Sa fety injection Pump Closed 2mC-6-066, 06/20/86 Test-I. Turbine Plant CCW Test Closed 2NRC-6-066, 06/20/86 -

Schedu le 10 Control Room Design Complete' 2 NRC-5-147, 12/02/85 Review (18.1) 2 m C-7-005, 01/08/87-2mC-7-466, 04/03/87 2NRC-7-100, 04/30/87

11. Safety Parameter Open'" 2NRC-5-151,12/20/85 Display System (18.2) 2mC-6-033, 04/09/86 2mC-6-064, 06/16/86 2NRC-7-063, 04/03/87
  1. Uncompleted sarveys will be a licensing condition.

' ## Resolution of open items by first refueling will be a licensing condition.

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 COMPLETED) 1 Operating Procedures Closed 2NRC-6-078, 08/04/86 for Continuous Communi- 2NRC-6-091, 08/19/86 cation Li n k s ( 2.2.2) l2 . Differential Settlement. Complete 2NRC-6-111, 10/23/86 of ~ Buried Pipes 2NRC-7-045, 03/09/87

-(2.5.4.3.3) 2NRC-7-058, 04/01/87

3. Internally Generated Complete 2NRC-7-058, 04/01/87 Missiles (Outside Con-tainment) (3.5.1.1) 4 Internally Generated Complete 2NRC-7-058, 04/01/87 Missiles (Inside Con-tainment) (3.5.1.2)
5. Turbine Missiles Complete 2NRC-5-157, 12/24/85 (3.5.1.3) 2NRC-7-033, 03/02/87 2NRC-7-095, 04/24/87 6 Analysis o f Pipe Break Complete 2NRC-7-058, 04/01/87 Protection Outside Con-tainment (3.6.1) 7 FSAR Drawing of Break Complete 2NRC-7-058, 04/01/87 Locat ions ( 3.6.2) 8 .Results of Jet Impinge- Complete 2NRC-7-058, 04/01/87 ment Effects (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 Components 2NRC-6-061, 06/06/86 (3.9.3.1) 11 Item 11.D.1 o f NUREG Complete 2NRC-5-157, 12/24/85 0737 (3.9.3.2) 2NRC-7-073, 04/10/87 12 Selsmic and Dynamic Complete 2NRC-6-075, 06/04/86 Quellfication of 2NRC-6-076, 08/04/86 Mechanical and Electrl- 2NRC-6-Il3, 10/27/86 cal Equipment (3.10.1) 2NRC-7-085, 04/16/87

F' ITEM- _ RESPONSE DATE NO.~ ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COmLETE)

13. Pump and Valve Oper- Complete 2mC-6-057, 06/04/86

- ability Assurance 2mC-6-076, 08/09/86 (3.10.2) 2NRC-6-113, 10/27/86 2mC-7-085, 04/16/87

14. - Environmental Quallfi- Complete- 2 NRC-6-053, 05/23/86 cation of Mechanical EC Audit, 11/18/86 and Electrical Equip- 2 NRC-6-121, 12/03/86 ment (3.11) 2mC-6-036, 03/04/87 -

15 Peak Pellet Design Closed 2NRC-5-132, 09/13/85 Basis (4.2.1) 16 Discrepancies In the Closed 2NRC-5-132, 09/13/85

~FSAR (4.2.2) 17 Rod Bowing Analysis Closed 2mC-4-102, 07/12/84 (4.2.3.1161)

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Fuel Rod Internal Pres- Closed 2NRC-5-132, 09/13/85 sure (4.2.3.1181)

19. Predicted Cladding Col- Closed 2mC-5-132, 09/13/85 lapse Time (4.2.3.2121) 20.' Use of the Square-Root- Closed 2mC-4-209,12/18/84 o f-t he-S um-o f-t he-Squares Method for Seismic and LOCA Load Calculation (4.2.3.3141) 21 ' Analysis of Combined Comp lete 2mC-6-002, 01/03/86 Loss-o f-Coola nt- Acci- 2 5 0-7-088, 04/22/87 dont and Selsmic dLoads (4.2.3.314I)

Natural Circulation Open 2 NRC 157, 12/24/85 A f te r Fue l 22.

Test (5.4.7.5) Load

23. Reactor Coolant System Closed 2mC 157, 12/24/85 High Point Vents (5.4.12) 24 . Blowdown Mass and Complete mR Action Only Energy Release Analysis Methodology (6.2.1.1; 6.2.1.3; 6.2.1.4)
25. Containment Sump 505 Complete 2 NRC 157, 12/24/85 Blockage Assumption 2 2 0-6-059, 06/06/86 (6.2.2) 2NRC-7-078, 04/13/87

-ITEM RESPONSE D ATE

~NO. ISSUE DLC STATUS' LETTER NO. AND DATE (IF NOT COM)LETE) 26 . Design Modification of Complete 2 NRC-6-067, 06/23/86

- Automatic Reactor Trip 2NRC-7-094, 04/24/87

- Using Shunt Coll Trip Attac heent . ( 7.2.2.3) 27 Automatic Opening of Closed Amend. 10, 05/30/8 5 Service Water System 2 NRC 157, 12/24/85 Valves MOV 113C and 1130 (7.3.3.10) 28 IE Bulletin 80-06 Con- Open 05/22/87 corns (7.3.3.13) 29 NUREG 0737 Item II .F.1, Closed 2 NRC-4-210, 12/18/84 Accident Monitoring 2NRC 157, 12/24/85 Instrumentation Post-tions (7.5.2.2) 30 Bypass and inoperative Complete 2 NRC-6-038, 04/15/86 Status Panel (7.5.2.A) 31 Revision of FSAR: Closed 2 NRC-6-066, 06/20/86 Cold Leg Accumulator Motor-Operated Valve Position Indication (7.6.2.4) 32 Control System Failure Complete 2 NRC 141, 10/15/85 Caused by Mal function 2NRC-6-054, 05/28/86 of Common Power Source 2 NRC-6-069, 04/07/87 or Instrument Line (7.7.2.3)

33. Confirmatory Site Visit I
a. Independence of Of f site Closed l Power Circuits Between

( the Swltchyard and Class t 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 l Quell fication Test

< (8.3.1.9)

RESPONSE DATE ITEM ISSUE DLC STATUS LETTER NO. AND DATE (I F NOT C006'LETE)

NO.

e. Margin Quali fication - Closed Test (8.3.1.10)
f. Electrical Interconnec- Closed tion Between Redundant

-Class IE Buses (8.3.1.13)

g. Veri fication of Elec- Closed trical Independence Between Power Supplies to Controls in Control Rocm and Remote Loca-tions (8.3.3.5) 34 Voltage Analysts -- Comp lete 2mC-7-092, 04/24/87 Veri ficaton of Test Result s (8.3.1.1)
35. Description and Analy- Complete 2mC-7-058, 04/01/87 sls of Compilance with GDC 50 (8.3.3.7.1) 36 Completion of Plant- Complete 2NRC-7-077, 04/13/87 Spect fic Core Damage Estimate Procedure Before Fuel Load (9.3.2.2) 37 Training Program for Complete 2mC-7-075, 04/13/87 the Operation and Maintenance 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 2mC-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 (l F NOT COWLETE)

-40 Solid Waste Process Open 05/15/87 Control Program (11.4.2)

- 41 TMI Action Plan items a.- t i l .D.1.1 (13.5.2) Complete 2NRC-6-080, 08/07/86 -

2mC-7-097, 04/29/87

b. II.K.1.5 and ll.K.1.IO Complete 2NRC 157, 12/24/85 (15.9.2; 15.9.3) 2m C-7-096, 04/29/87
c. II.K.3.5 (I5.9.9) Complete 2NRC-7-098, 04/22/87
d. II.K.3.17 (15.9.11) . Comp lete 2 mC-5-157, 12/24/85 2 mC-7-059, 04/01/87
e. II.K.3.31 (15.9.14) Closed WCAP-IOO54 WCAP-10079 EAP-11I45 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 Complete SGTR-86-001, 02/28/86 Rupture (15.6.3) 44 Quality Assurance Closed 2NRC-5-096, 06/28/85 Program (17.5) 2mC 152, 12/20/86 45 Cross-Training Program Closed 2NRC-6-073, 07/22/86 46 Control Room isolation Complete 2 mC 108, 10/16/86 On High Radiation 2 5 0-7-044, 03/09/87 Signal 47 ER Review of PGP for Comp lete 2 5 0-7-071, 04/08/87 E0Ps (13.5.2)

-48 Fire Protection: Amendment 12 review and site visit a) Amendment 12 review Closed 2mC-6-066, 06/20/06 b) Site Visit Complete 2NRC-7-026, 02/11/87 2mC-7-040, 03/05/87 c) Safety related system Complete 2mC-7-003, 01/06/87 fire barrier deviations 49 Stoam generator high-level Complete 2mC-6-087, 08/12/86 trip as non-protection 2mC-6-039, 03/04/87 system 50 Imp leme nta t ion letter of Open TBD ICCI System St. Superheated steam In valve Complete 2NRC-6-099, 9/20/86 krg due to steamline g ,6-g j , gj g gf

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< ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. AND DATE (IF NOT COWLETE) 52 Initial Testing

a. Accumulator isolation Open Prior to mode 3 Valves
b. SOV, PO IS tests Comp lete 2m C-7-004, 01/12/87
c. Plant Perfomance after Complete 2 NRC-7-033, 03/02/87
  • MSly closure
d. Steam Extraction System and - Complete 2mC-7-033, 03/02/87 Process Computer I

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ATTACHMENT 3 -

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. SAFETY EVALUATION REPORT REVIEW STATUS TABLE 16.0 TECHNICAL SPECIFICATIONS

.' ITEM

0, ISSUE' DLC STATUS LETTER NO.' AND DATE REMARK S 1 Initial Draft Sutalttal Cm plete 2NRC-4-144, 09/14/84
2. Pre-issue Revision l Complete 2mC-5-153,12/20/85
3. Response to Request for Ca plete 2 mC-6-044, 05/06/86 Additional Information 4 Informal meeting ' Complete with reviewer July,1986 5 Comments on NRC Initial Complete 2mC-6-120,11/28/86 Awaiting M C

. Draft of BV-2 Tech 3pecs issue of " Proof.

and Review" copy of By-2 Tech Soecs

.?: ATTACHMENT 4 REQUEST FOR ADDITIONAL INFORMATION RESPONSE DATE DATE SUBJECT DLC STATUS LETTER NO. AND DATE (IF NOT COWLETE) 03/03/86 Inadequate Core Cooling Closed 2mC-6-037, 04/11/86 2mC-6-075, 07/31/86 04/03/86 ATWS Closed 2NRC-6-063, 06/16/86 2mC-7-091, 04/24/87 04/22/86 RCP Trip Criterla Cm plete 2mC-7-089, 04/22/87 05/23/86 Control Rom Isolation Cm plete 2 NRC 108, 10/16/86 On High Radiation 2m C-7-044, 03/09/87 06/27/86 ATWS Complete 2WC 109, 05/07/87 06/30/86 S.G. Level Control Cmplete 2mC-6-OP7, 08/12/86 11/26/86 Inservice Testing Cm plete 2NRC-7-084, 04/15/87 12/03/86 Confirmatory issue 47 Open 03/27/87 ,

'02/11/87 Plant Safety Monitoring Comp lete 2 2 0-7-101, 04/30/87 System Veri fIcatlon and v Validation 02/27/87 Confirmatory issue 32 Open 03/27/87 03/05/87 Confirmatory issue 14 Complete 2NRC-7-036, 03/04/87 03/11/87 Initial Test Program Open 05/22/87 03/20/87 Of f site Medical Services Complete 04/02/87 For Emergency Preparedness l

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ATTACHMENT 5

- FSAR #4ENDENTS

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AMENDMENT TRANSMITTAL LETTER RTIFICATION LETTER

' NUMBER NUMBER & DATE- NUMBER & DATE

'l 2NRC-3-028, 05/16/83 2mC-3-031, 05/19/83

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2 2NRC-3-043, 07/14/83 2NRC-3-050, 07/22/83 3 i ' 2NRC-3-077, 10/26/83 2mC-3-085,11/04/83 4 2 NRC-3-096, 12/02/83 2 2 0-3-100, 12/13/83 5 2NRC-4-011, 02/09/84 2mC-4-025, 03/09/84 .

6 2NRC-4-048,04/27/84 2 mC-4-054, 05/09/84 7 2NRC-4-098, 07/02/84 22C-4-103, 07/13/84

.8 2NRC-4-154, 09/25/84 2 mC-4-161, 10/08/84 9 2NRC-4-210, 12/18/84 2mC-4-213,12/27/84 10- ' 2NRC-5-075, 05/20/85 2 NRC-5-087, 06/07/85 11 2NRC-6-010, 01/28/86 2NRC-6-012, 02/04/86 12 2mC-6-066, 06/20/86 2mC-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- 22C-7-022, 02/04/87 15 2NRC-7-033, 03/02/87 2mC-7-037, 03/04/87 t

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