ML20113A502
| ML20113A502 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/14/1985 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-5-005, 2NRC-5-5, GL-82-33, NUDOCS 8501210126 | |
| Download: ML20113A502 (7) | |
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'Af 2NRC-5-005 g gg q-(412) 787-5141 (412) 923-1960 Nuclear Construction Division Telecopy (412) 787-2629 Robinson Plaza, Building 2. Suite 210 Pittsburgh, PA 15205 January 14, 1985 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. George W. Knighton, Chief Licensing Branch 3 Of fice of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docke t No. 50-412 S.E.R. Outstanding Issues Status Gentlemen: is a current list, as of January 11, 1985, which pro-vides our understanding of the 58 outstanding issues which remain open. In order to pe rmit timely resolution of items ident i fied which may not be resolved to the staf f's satisf action, please provide a specific description of the issue which remains to be resolved.
Please provide a schedule for providing the following items:
Safety Evaluation for Issues Identified in Generic Letter 82-33
- Safety Evaluation Report Safety Implementation Report for SPDS
- Advisory Committee on Reactor Safeguards DUQUESNE LIGHT COMPANY e, [4 s4
-/
/
By E. J. Wf'olev&/
Vice Pfesident GLB/wjs A t tachment Mr. H. R. Denton, Director NRR (w/ attachment) cc:
Mr. D. Eisenhut, Director Division of Licensing (w/ attachment)
Mr. B. K. Singh, Project Manager (w/ attachment)
Mr. T. Novak, Assistant Director Division of Licensing (w/ attachment)
Mr. G. Walton, NRC Resident Inspector (w/ attachment)
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1 ATIAQMNT 1 OUISDWOIIC ISSLES PROPOSED OUISIAIOD C leC ASSOCIATED RESmtE ISSLE SU!UECT IRUG QUES 110N
- DATE STATUS IEITER 10. AIO DATE 1 (158)
IMV setpoint values (5.2.2.2)
RSB 03/31/86 Confirmatory 2NRC4-122, 08/10/84 2 (161)
Qualification of IIHR ptmps inside contairument (5.4.7.4)
RSB Clasai 2 FRO 4-122, 08/10/84 3 (162)
Natural circulation test (5.4.7.5)
RSB 440.75 01/18/85 B
2fRC-4-122, 08/10/M 4 (163)
Programs and procedures for contairment stap operation (6.3.1)
RSS 440.35 C1csa!
2 2 0-4-122, 08/10/84 5 (200)
Infonnation on evaluations of individual everts (15)
RSB 440.1 Closal 2?R04-122, 08/10/84 6 (201)
Turbine trip event (15.2.3)
RSB 440.1 Clossi 2?RC4-122, 08/10/84 7 (202)
Reactor cool et pump rotor seizure (15.3.3/
15.3.4)
RSB Closal 2?RO4-122, 08/10/84 8 (203)
Inadvertant boron dilution durirg refuelirs (15.4.6)
RSB 440.59 Confinnatory 2:R04-122, 08/10/84 9 (103)
Radiological consequences of a steam genera-tor tube rupture DBA ard review of operator actions and systen perfonmance (15.6.3 &
T15.1)
AEB D
2fR04-086, 06/20/M 10 (59)
Service water systen isolation on low header 2fRC-4-086, 06/20/%
Fessure (7.3.3.4)
ICSB Classi 2?RO-4-141, 09/10/84 2fRC-4-202,12/05/84 11 (%)
Stems generator level control arti protection (7.3.3.12)
ICSB F
2?RO-4-068, 05/30/84 12 (71)
Bypass and inoperable status p eel (7.5.2.4)
ICSB Closed 2rRC-4-079, 06/13/M 2?RO-4-165,10/11/84 2150-4-1%,11/27/M
I
- ~
PROPOSED OUTSDUDUC 18C ASSOCIATED RESP 0 LEE TcJilE
!EIVECT 1EAIGI QUESTION DATE STATUS IIITER 10. APO DATE 13 Internally generated missiles outside containeert (3.5.1.1)
ASB H
2 2 0-54)03, 01/08/85 14 Internally serwrated missiles inside containemt (3.5.1.2)
ASB H
2 2 0-54)03, 01/08/85 15 433)
Protection against postulated pipe breaks outside containment (3.6.1)
ASB confirmatory 22 0-54)03, 01/08/85 15(134)
Fuel pool maxima heat lomis (9.1.3)
ASB F/R 2!aC-4-085, 06/15/84 2rRO-5-003, 01/08/85 17 Overhead heavy-loal handlirs systen (9.1.5)
ASB 01/18/85 G
18 (137)
Marine growth in standby service water H
2mO4-099, 07/02/84 systen (9.2.1.2)
ASB 410.7 21ec-54)03, 01/08/85 19 Primary ON system (9.2.2.1)
ASB 410.55 01/18/85 G
20 (148)
Water hammer test of he and feed-uter system (10.4.7)
ASB 410.44 H
2mO4-121, 08/13/84 2:ec-5-003, 01/08/85 21 (149)
Auxiliary feeduster systen,1MI Itea 2fec-4-099, 07/02/84 II.E.1.1 (10.4.9)
ASB Closed 2rRO-5-003, 01/08/85 22 (46)
Ioose parts detection progran report (4.4.5)
&B 02/28/85 E
225 0-4-167, 10/12/84 23 (47)
TWee core cooling instrumentation (Item II.F.2 of NLRfD-0737)
&B 03/31/85 E
24 (153)
Analysis of combined LOCA ad seismic lomis (4.2)
GB Closed 2m04-209,12/18/84 25 On-line detection method CPB Closed
I
_3 l
PR@0 SED OUIS1NOI!C IWC ASSOCIATED IESPONE YMR R ETECT 5 TAN 01 QUESTION DATE SDLTUS LETIER 10. AIO DATE 26 X/Q
}EIB F
21W0-4-189,11/08/84 27 (115)
Snowpack load on roofs (2.3.1) lEIB 21eo-4-112,07/30/84 28 (105)
Radiological consequences of a loss of coolart DBA (15.6.5 & T15.1)
AEB F
2fR04-153, 09/25/M 29 (101)
Radiological consequences of control rod ejection DBA (15.4.8 & T15.1)
AEB F
2fR04-153, 09/25/M 30 Primary vs. amerniary loads (3.9.3)
EB 210.39 01/23/85 E
31-32 (43)
Preservice avi inservice testing of pumps 2!aC-4-096,06/29/84 axl valves (3.9.6)
IEB 210.41 a-06/85 E
2 FRO-4-097, 07/02/84 210.40 b-01/31/85 E
2feO4-184,11/07/84 c-06/85 33 Asymmetric IOCA loais (3.9.3)
EB 210.42 D
34 (13)
SRP 3.7.1 (Al 1): (a) Exceedece of verti-cal response spectra (7-10Hz, Fig. 9-1 of Jtne 19% report suhaitted by Dic); (b) sub-2tR04-047, 04/27/84 ject to Geosciences Branch approval 92B 220.4 02/01/85 Confirmatory 2 rec-4-072,06/01/84 35 (15/16)
SRP 3.7.3 (AI's 4, 7, & 23): (a) Perfor-mance of the half-space (unbotnded) SSI method for the contairument mul intake struc-tures; (b) Use irpte from (a) to address Items 4, 7, & 23. There is no need to STB 220.5/.6/
ad&ess amiliary buildirg gain.
.7/.8 01/18/85 E
2 FRO-4-080, 06/15/84 36(18)
SIP 3.8.1 (Al 10): For different loal cate-spry, use direct comparison to show that BV-2 seets the criteria of liner strain allowable mi the liner an6or alloud>1e as speified in A9E Div. 2 Tables 00-3720-1 2PR04-080, 06/15/84 awi CC-3730-1, respectively SCEB 1
21eC-4-212,12/21/84
-s-PROPOSED OUEStWODO lac ASSOCIA~RD RESPOIEE mir Sunscr muGI QUESTIN MTE SETUS IETIER 10. AIO ME 37(20/21)
SRP 3.8.3 (Al 15): Prwide the governirg load cambinations for differert parts of the internal structures and show they are cose-patible to those of ACI-349 ard RG 1.142; (Al 13): Stimission of final results of the confimation Irogram to verify the design of the contairment's internal structure (includirg steam generator cubicles) for final presswe loads; (Al 28): Clarifica-tion is needed to explain dry the ef fects of Ta are of to importece. You have irdicated in your thennal transiest analysis that themal strain = 0.001 and concrete allouable strain = 0.003; (Al 27): (1) AE of two seismic Pts vs. SRSS of three seismic camponerts on polar crane. That to 2:R04-047, 04/27/84 show ABS is equally conservative as SRSS; 215 0-4-207, 12/17/84 (2) Use the irptc fras SRP 3.7.3.A, B in (1)
SCEB 1
2 FRO-4-212,12/21/84 38 (21)
SRP 3.8.4 (Al 19): Submit a typical calcu-lation analysis to show the seisade wave effect on conduits at bends and tees; (Al 22): Prwide hes to show that the existirg design margins with the refueling water storage tark md the grimary dominer-alized water storage tark can acer=mdate 2rRO4-047, 04/27/84 the increased loads due to timk unit 21ec-4-080,06/15/84 flexibility SEB 1
2 FRO 4-207,12/17/M 39 (16/23)
SRP 3.8.5 (AI's 6 & 7): Safety factors gainst slidirg and werturnirs for the con-tainmert ard intake structurm. 'three cam-2 FRO 44)47, 04/27/%
ponent earthquake input frain 3.7.3.A should 2!aC-4-080, 06/15/%
be used in the assesamert SEB Confinnatory 2 FRO 4-207,12/17/%
PRTOSED Outst4 DIM; MIC ASSOCIATED RESPONiE ISsus a aIECr BANN QUESTION MIE S111US IETIER m. AE MIE 40 (6/7/8 Seimnic Design Response Spectra CB 230.3/.4/
02/01/85 E
2Mic-4-048,04/27/84
/9/10)
.6 2Mt0-4-072, 06/01/84 41 (150)
Seismic qualification of equipment EQB 08/85 Confirmatory 2MtC-4-118, 08/05/84 2ASR-01501, 09/18/M 42 (151)
Ptsp avi valve operability assuraice pmgram IQB 271.1.14 08/85 Confinnatory 2MtC-4-118, 08/05/84 2ASR-01501, 09/18/%
43 (152)
Envirormental qualification of equipment EQB 271.1.14 11/85 Confirmatory 2mC-3-096,12/05/83 44 (48)
Preservice inspections program (5.2.4.3)
MIEB 06/85 E
2Mto-4-096, 06/29/84 45 (54)
Inservice inspection of Class 2 avl 3 MIEB a-6/85 E
2MIC4-096, 06/29/84 Ps (6.6) c--6/85 46 (156)
Ihlercial cracking of forgings in reactor vessel (4.2.3, 4.3.1.2)
MrEB Closed 2Nt04-120, 08/10/84 47 (85)
Safe shutdoun (9.5.1/C.S.b)
OlEB A/E l
48 (86)
Alternate shutdown (9.5.1/C.5.c)
OEB A/E l
49 C&le sprealirg room 01EB F
2NtC-4-067, 05/30/84 50 (1)
Potential for flooding from local intense precipitation (2.4.2.3)
DEB 240.8 F
2Nt04069, 05/30/M 51 (2)
Floodirg from Peggs Run (2.4.2.3)
DIEB 240.1 F
22C4-069, 05/30/84 52 (3)
Adarp= y of the proposed teds spec for drought coniitions (2.4.11.2)
HIEB Closed 2 2 0 4-049, 04/30/84
-3 fFDS awl QlDR (St9pleent to 0737)
HFEB 420.01/
E 620.01.04 54 Crose-trainirg program (13.2.1.2) 1@
C l
l l
y -
P90E06ED OU"SnuelE leC ASSOCIATED RESE0 TEE ISSE SUILIECT NNDI QtESITGI MTE STATUS LEITER 10. A10 M1E 55 Management and orgmization iip E
56 Initial test program PSRB 01/31/85 E
57 Buergency operating procedures PSRB E
58 (165)
On-site _#cj plamiqr, (13.3.2)
EPLB 03/01/85 E
2fec-4-130, 06/31/84 A - leC IM agreed to casbine into one iten B-Ttree alditional questions were sent to applicant; will close after resp >nse is received; one response received C - T. Novak agreed to resolve reviewer responsibility D - Generic issue E - Applicart has to prwide alditional infonsation F - Applicat has identified as backfit ites; will close after appeal G-Applicart will grwide alditional infonastion as per telephone conference call on 11/01/84 H - Applicat has provided additional infonmation as per telephone confererce call cn 11/01/84 I-Dtf consilers this itan satisfactorily closed smiess notifief otherwise by the IRC
- Power Systass aseting scheduled for 01/28/85