ML20212D376

Forwards Five Current Lists,As of 861201,providing Understanding of SER Outstanding Issues.Items Considered Satisfactorily Closed

ML20212D376
Person / Time
Site:	Beaver Valley
Issue date:	12/23/1986
From:	Carey J DUQUESNE LIGHT CO.
To:	Harold Denton, Tam P Office of Nuclear Reactor Regulation
References
2NRC-6-128, NUDOCS 8612310348
Download: ML20212D376 (12)

Text

I ar, M 2NRC-6-128 Beaver Valley No. 2 Unit Project Organization Telecopy Ext.160 S.E.G. Building P.O. Box 328 Dec. 23, 1986 Shippingport, PA 15077 Mr. Harold R. Dentaa Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTIQ4: Mr. Peter Tam, Project Manager Division of PWR Licensing - A (ffice of Nuclear Reactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 S.E.R. 02tstanding issues Status Gentlemen:

Attached are five current lists, as of December 1,1986 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 satisf actorily 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-ment of status described on the attached list.

DUQUESNE LIGliT C OtPANY By u Q/ J. Carey*'

Senior Vice President RWR/ijr NR/ ISSUE / STATUS Att tents AR/

i cc: Mr. J. Beall, Senior Resident inspector - w/ attachments Mr. L. Prividy, Resident Inspector - w/ attachments OA12310348 061223 PDR ADOCK 05000412 E PDR

t ATTAC M NT 1 SAFETY EVALUATION REPORT ,

REVIEW STATUS TABLE 1.2 OPEN l$$lES ITEM RESPONSE DME NO. ISSUE OLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE)

I 1 Preservice/I nservice Testing (3.9.6)

a. Preservice Testirg Del eted 2NRC-5-154,12/26/85 5 2NRC-6-034, 04/09/86

b. Inservice Testing Open TBD i

2 Pump and Valve Leak Closed 2NRC-6-005, 01/09/86 Testing (3.9.6)

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, 3. ICC Instrumentation Closed 2NRC-5-079, 05/31/8 5 (item i t.F.2 of NutEG 2NRC-6-037, 04/11/86 4 0737) (4.4.7) 4 Preservice/ inservice Open 2NRC-5-154, 12/26/85 03/31/87 l Inspection Progran i

(5.2.4.3; 5.4.2.2; 6.6)  ;

4 5. Safe and Alternate Open 12/15/86 Shutdown (9.5.1) 6 Management and Organi- Under NRC 2NRC-6-097, 09/18/86 zation (13.1) Review 7 Cross-Training Program Closed Carey to R. M. Keller

) ( 13. 2.1. 2) Letter 06/13/85 i 8 Emergency Preparedness Cont Irmatory 2NRC-5-077, 05/28/85

, Plan (13.3.3) 2NRC-6-092, 08/22/86

, 9 Initial Test Program l (14)

a. Remote Shutdown Test Closed 2NRC-5-110, 07/29/8 5 l

j 2NRC-6-066, 06/20/06 l b. Test Acceptance Closed 2NRC-5-110, 07/29/85 Criteria i

c. NUREG 0737 Item 1.G.1 Cl osed 2NRC-5-Il0, 07/29/85 4 2NRC-6-066, 06/20/86 i

d. Rollet and Dump Valve Closed 2NRC-5-110, 07/29/85

! Capacity Tests 2NRC-64)45, 05/06/86 i

e. Test Classification Closed 2NRC-5-110, 07/29/85 DI screpa ncies i

f. g u g e isolation Closed g g - g , g7/g /g i

- . , _ _ . , . _ , - - - _ _ - - . . _ . . .,.__m-.----_._ .,,,--,-~._____,,._._,,_.-_._.__._.m-- - . . . . , , - , - , . . _ - . , _ - . . . _ . . . _ ~ . . - , m, .c,

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BTEM RESPot4SE DATE HO. ISSUE DLC STATUS LETTER NO. AfD UATE (IF NOT COMPLETE )

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

2NRC-6-070, 06/21/86 i

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h. Safety injection Pump Closed 2NRC-6-066, 06/20/86 1 Test i

l. Turbine Plant CCW Test Closed 2NRC-6-066, 06/20/86 j Schedul e i 10 Control Room Design Open 2NRC-5-147, 12/02/85 01/07 Rev i ew ( 18.1)

11 Sa f ety Parameter Complete 2NRC-5-151, 12/20/65 l Display Syste (18.2) 2NRC-6 033, 04/09/86 j 2NRC-6-064, 06/16/85 1-i i

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ATTACHMENT 2 SAFETY EVALUATION REPORT REVIEW STATUS TABLE 1.4 CONFlie4ATORY iSSLES BTEM .

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

1 Operating Procedures Closed , 2NRC-6-078, 08/04/86 i for Continuous CommunI- 2NRC-6-091, 08/19/86

. cation Li nks (2.2.2) 2 Differential Settlement Open 2NRC-6-Ill, 10/23/86 03/31/87 3

of Huried Pipes

(2.5.4.3.3)

, 3 Internally Generated Open

! Missiles (Outside Cor*

talrment) (3.5.1.1) i j 4 Internelly Generated Open Missiles (Inside Core ,

talreent) (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 Protectlon Outside Core tainment (3.6.1) i

!' 7 FSAR Drawlng of Break Open

• Locations (3.6.2)

8. Results of Jet Impinge- Open i ment Et fects (3.6.2) 9 Soll Structure inter- Closed 2NRC-5-lle, 08/07/85 action Analysis (3.7.3) i 10 Design Documentation of Closed 2NHC-6-001, 01/03/86 ASME Code Camponents 2NRC-6-061, 06/06/86

! (3.9.3.1)

11. Itan ll.D. ] of NUREG Complete 2NRC-5-157, 12/24/85 1 0737 (3.9.3.2) l 12 Selsmic and Dynamic Complete 2NRC-6-057, 06/04/06 I

Quali fication of 2NRC-6-076, 08/04/66 i Mechanical and Electrl- 2NRC-6-ll3, 10/27/86 cal Equi pment (3.10.8)

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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 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 NRC Aud i t, 11/18/86 and Electrical Equi p-ment (3.11) 15 Peak Pellet Design Closed 2NRC-5-132, 09/13/85 Bnsis (4.2.1) 16 Olscrepancies 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) 18 Fuel Rod internal Pres- Closed 2NRC-5-132, 09/13/8 5 sw e (4.2.3.1181) 19 Predicted Claddi ng Col- Closed 2NRC-5-132, 09/13/85 lapse Time (4.2.3.2121) 20 Use of the Square-Root- Cl osed 2NRC-4-209,12/18/84 o f- t h e-S um-o f- t h e-Squares Method for Se i smic a rd LOC A Load Calculation (4.2.3.3l41) 21 Analysis of Combined Complete 2NRC-6-002, 01/03/86 Los s-o f-Coo l i nt- Acc i-dent and Selsmic dLoads (4.2.3.3141) 22 Natural Circulation Open 2NRC-5-157, 12/24/85 01/31/87 Test ( 5.4.7.5) 23 Reactor Coolant System Closed 2hRC-5-157, 12/24 /85 High Point vents (5.4.12) 24 Blondown Mtss a nd Com pl ete NRR Action Only Enengy Release Analysis Methodology (6.2.1.1; 6.2.1.3; 6.2.l.4) 25 Contai nment Samp 501 Open 2NRC-5-157, 12/24/85 01/30/87 Olockage Assumption 2NRC-6-059, 00/06/86 (6.2.2)

, -3 ITEM RESPONSE DATE

& ISSui OLC STATUS LETTER NO. AND DATE (IF NOT COMPLETE) 26 Design Modification of Complete 2NRC-6-067, 06/23/86 Automatic Reactor Trip Using Snunt Coll Trip

• Attachment (7.2.2.3) 27 Automatic Opening of Closed Amend. 10, 05/30/85 Service Water Systen 2NRC-5-157, 12/24/85 Valves MOV 113C and 1130 (7.3.3.10) 28 IE Bulleti n 80-06 Cor>- Open 12/31/86 corns (7.3.3.13) 29 NUMEG 0737 Item il.F.1, Closed 2NRC-4-210, 12/18 /84 Accident Monitorirg 2NRC-5-157, 12/24/85 Instrumentation Post-tions (7.5.2.2) 30 Bypass and inoperative Complete 2NHC-6-038, 04/19/86 Status Panel (7.5.2.4)

31. Revision of FSAR: Closed 2NRC-$-066, 06/20/86 Cold Leg Accumulator M) tor-Operated Valve Position Indication (7.6.2.4) 32 Control System Failure Complete 2NRC-5-141, 10/15/85 Caused by MeIf unctlon 2NRC-6-054, 05/28/86 of Common Power Source or Instrument Li ne (7.7.2.3) 33 Confirmatory Site visit

a. Independence of Of f site Closed Power Circuits Between the Switchyard and Class IE Systen (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 Quali fIcation Test

! (8.3.1.9) i 4

e ITEM RESPONSE DATE (IF NOT COMPLETEl

& ISSUE OLC STATUS, LETTER NO. AND DATE (i e. Mergin QuelltIcation Closed Test (8.3.1.10)

f. Electrical interconnec- Closed tion Betesen Redundant Class 1E Huses (8.3.1.13) j g. VerifIcatlon of Elec- Closed

trleal independence

! Between Power Supplies to Controls in Control Roan and Renote Loca.

tions (8.3.3.5) i 1

34 Voltage Analysis -- Open Approx. 6 Months verificaton of Test Prlor To Fuel I

Results (8.3.1.1) Load f

Description and Analy- Open **

l 35

) als of Conpliance with j GDC SO (8.3.3.7.l)

! 36 Conpletion of Plant- Open 12/31/86 j Specific Core Damage i Estimate Procedure i Before Fuel Lost 1

l (9.3.2.2)

' 12/86 37 Tralning Progran for Open i the Operation and Maintenance of the

. Diesel Generators I

(9.5.4.1) 38 Vibration of Instru. Open Fuel Load monts and Controls on Olesel Generators (9.5.4.1) i i 39 Surveillance of Lube Closed 2NHC-6-029, 03/26/86 l 018 Level in Olesel l Generator Rocker Arm i Lube Oil Reservoir I (9.5.7) i i

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ITEM RESPONSE DATE LETTFR NO. AND DATE (IF NOT COMPT.FTF) 1 ISSUE OLC STATUS 40 Solid Weste Process Open 05/15/87 I Control Progran (11.4.2)

41. TMl Action Plan ites

e. 111.D.1.1 (13.5.2) Open 2NRC-6-080, 08/07/86 90 days prior to Fuel LoadI ng

b. I I .K. l .5 a nd l l .K l .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) Open 01/31/87

d. II.K.3.17 (15.9.11) Open 2NRC-5-157, 12/24/85 01/30/87

e. II.K.3.31 (15.9.14) Closed WCAP-10054 WCP-10079 WCAP-l ll45 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 $GTR-86-001, 02/28/86 TB0 Ruptwe (15.6.3) 44 Quality Assurance Closed 2NRC-5-096, 06/28/8 5 Progren (17.5) 2NRC-5-l52, t2/20/86

45. Cross-Tralning Progran Complete 2NRC-6-073. 07/22/86 46 Control Room isolation Compl ete 2NRC-6-108, 10/16/86 On High Radiation Sig nal

47. Pe<R Review of F'GP for Compl ete NRR Action Only EUPs (13.5.2) 48 Fire Protection: Amendment 12 rwiew an1 site visit a) Amendment 12 rwlow Closet 2NRC-6-066, 06/20/86 b) Site Visit Open 02/87 c) Safety related systen Ope n 12/31/86 fire barrier deviations 49 Steam generator high-level Compl e te 2NHC-6-087, 08/12/86 trip as nor> protection systen 50, impi snentation letter of Open TB0 ICCI Systen

51. S sperneated steen in valve Open 2NRC-6-099, 9/20/86 prior to f uel losii ng gsj due to steanline

6=

ITEM RESPONSE DATE NO. ISSUE DLC STATUS LETTER NO. ANO DATE (IF NOT COMPLETE) 52 Initial Testi ng I

a. Accumulator isolation Ope n Prior to mode 3 valves

b. SUV, PO IS tests Ope n FSAR Amendment 13

c. Plant Performance af ter Open FSAR Amendment 14 MSiv closu*e

d. Stesa Extraction Systen and Ope n FSAR Amendment 14 Process Computer

• Hazards analysis 15 scheduloj for completion at the end of 1986 and documented in early 1987 ce To be includes in FSAR Amendment 13, Decunber 1966 O

r ATTACHMENT 3 SAFETY EVALUATION REPORT REVIEW STATJS I

TABLE 16.0 TECHNICAL bPECIFICAil0NS ITEM NO. ISSUE DLC STATUS LETTER NO. AND DATE REMARKS

1. Initial Draf t Submittal Compl ete 2NHC-4*144, 09/14/84 Ana l t i ng NRC

.Sct io n

2. Pre-issue Revision I Complete 2NHC-5-153, 12/20/oS Awaiting NRC Act ion

3. Response to Request for Complete 2NRC-6-044, 05/06/86 Awelti ng N4C Addi t io nal I nforma tion Act ion 4 In f ormal meet i ng Complete Awe l t i ng NRC wi th re<l ower Jul y,1966 Action l

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ATTAC M NT 4 NEQUEST FON AD06T10NAL 1NFORMAT10N

+

i RESPONSE DATE DATE SullJECT DLC STATUS LETTER NO. AND JATE (IF NOT COWLETE)

I

' -03/03/86 Inedequete Core Cooling Closed 2NRC-6-037, 04/11/86 2NRC-6-075, 07/31/86 i 04/03/86 ATwS Complete 2NHC-6-063, 06/16/86 ,

t-j 04/22/86 HP Trip Criteria 01/30/87 05/23/86 Control Room loolation Complete 2NHC-6-108,10/16/86 On High Radiation 4

06/27/86 ATWS 02/01/87 .

t 06/30/86 S.G. Level Control Complete 2NRC-6-067, 08/12/86 2

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FSAR AMIENOMENTS .

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AIENUMENT TRAN$MITTAL LETTER CERTIFICAT10N LETTER i

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M NuteER & OATE '

NU0SER & DATE > /

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1 2NMC-3-028, 05/16/83 2NMC-3-031, 05/19/83,... f

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2 2NRC 'a-043, 07/14/83' ,

2NRC-3-050, 07 N /J3 (

y> / o, -

1. s 3 2NPC-3-077, 10/26/83 2NHC-)-085, 11/04/83 s r 4 2NRC-3-096, 12/02/83 ,2MC-J-100, 12/13/8 3 8

? s 2NRC-4-Oll, 02/09/84 'MC-A-025, 03/09/64 '-

5 6 2NHC-4-048, 04/27/84 2NRC-4-054, 05/09/84 1 ,

h 7 2NRC-4-096, 07/02/64 2NHC-4-103, 07/13 '8 4 i' ,

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8 2NRC-4-154, 09/25/84 2NRC-4-16 l,10/08/d 4/

9 2NRC-4-210, 12/13/84 We4C-4-213, IN2i/P4 10 2NRC-5-075, 05/20/85 De4C-5-087, Do/17/P 5 7 :-

i il 2NRC-6-010, 01/28/66 2NHC-6-012, 02/04/66 " t l l

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12 2NHC-6-066, 06/20/86 2NHC-o-Giu, 06/27/66 ) .,

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