ML20084M996
| ML20084M996 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/08/1984 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-4-053, 2NRC-4-53, GL-84-08, GL-84-8, NUDOCS 8405160255 | |
| Download: ML20084M996 (4) | |
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2NRC-4-053 (412) 787 - 5141 Telecopy 7
9 Nuclear Construction Division May 8, 1984 Robinson Plaza, Building 2, Suite 210 Pittsburgh, PA 15205 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. Thomas H. Novak Assistant Director for Licensing Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Do cke t No. 50-412 Significant Licensing Issues Gentlemen:
In early March 19 83, I was informed of your des ire to meet with Duquesne Light Company (DLC) u ppe r management to discuss the licens ing s t atu s of Beaver Valley Power Station Unit 2 (BVPS-2).
The meeting was tentatively scheduled for March 21, 1984, here in our proj ect offices in Pittsburgh. At the request of George W.
Knigh ton, in preparation for this meeting, a list of significant licens ing issues on BVPS-2 was provided to our NRC Proj ect Manage r.
Sho rtly thereaf ter, we were info rmed that the meeting had to be postponed.
The at t ached lis t of Significant Licensing Issues is provided fo r your review.
We fe el that these items have the pot ent ial for significant impact on the BVPS-2 licensing schedule atd that a significant po rt io n of the res pons ibility fo r reso lving the issues falls upon the NRC.
Many of these issues will require your evaluat ion as described in Generic Letter 84-08.
The impact of these issues upon issuance of the SER and the schedule for ACRS must be discussed.
We request that the meeting be rescheduled with DLC management for the earlies t possible date. We sugges t that the attached list of licensing issues serve as the agenda for discussion at the meeting.
A discussion of the schedule for providing remaining draf t SER sections as reques ted in our March 30, 1984, letter to G.
W. Knighton is also ap propriate.
DIE will provide whatever cooperation is necessary to accommodate your schedule.
DUQUESNE LIGHT COMPANY By E. VI."Wooleve r Vice President 8405160235 840508
{DRADOCK05000 OOl 1' i
United States Nuclear Regulatory Commission Mr. Thames H. Novak i
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t-l-
GLB/wjs At t achment cc; Mr. H. R. Denton, Director NRR (w/a)
Mr. D. Eisenhut, Director Division of Licensing (w/a)
Mr. G. W. Knighton, Chief, Licensing Branch 3 (w/a)
Mr. G. Walton, NRC Res ident Inspector (w/a)
Mr. M. Lacitra, Project Manager (w/a)
Ms. M. Ley, Proj ect Manager (w/a)
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BAmFIT ITEMS 10
' IT!!M SOUR 2 RBGUIATORY BASIS EST. 00b7 N-2 POSITICN
'l pacane studies of "PPF indicate edi-Q240; SER OI 1&2 2ne (Extension of SRP) 50,000 Use of new, extremely conservative hydro set 1 fication of existirg door may be :
study is beyoni scope of SRP ard has not been required justified by MtC.
2 Provide low-level alana for rocker arm Q430.119 2ne (SRP 9.5.7) 50,000 cole diesels stilize low p esstre & hi-level 1the oil resevoir alanns in the rocher ann area.
-:3 Addition of cartrol roan ireake radia-Q410.7, 28 & 53;
@c 19, 0737 III.D3.4 100,000 BV-2 has recire duct nonitor gerator action tion u nitors SRP 6.4; SER OI 53 to isolate on various radiation alama is aiequate.
4 Diesel air dryers Q430.97 & 100 Pbne (SRP 9.5.6) 500,000 Adequate refundancy exists. Ops. ani mairt.
}ractices at BV-1 are successful BV-2 desigt.
is nore tolerart of noisture. Ib requirenert exists.
5 Addition of accumulator isolation SER OI 67 Pbne valve position indication 6
Camponert. coolirs water flow instrtsmen-Q410.19 & 21
@C 44 (SRP 9.2.2.1) -
Sufficiert operator info is available. Multi-tation pie locksi rotors is unlikely.
7 Intentially deleted 8
Heavy loads upgrade 1/17/84 letter Restrictive (see GL 81-07); None (SRP 9.1.5) j
- 9 Addition of fotrth stem generator.
9/19/83 letter; 1EEE 279-1971 IEEE nd applicable to this function.
level chanel SER OI 64 10 Addition of P-4 testirg provision' ICSB SER 0157 Ibne 11 Open items front structural axiit SER OI 21 lbne 12 W-1 intake structure analysis SER OI 23 Struct.
Ibne Intake Structtre Lic. on BV-1 doclet.
Audit
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. 13 Tlech Specs, Rev. 0, vs new. 4 :
Ntc Mtg 8/83 lbne' 4
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4r 6-
BAmFIT 1HMi (continued) 10 11TM SOURG REGUIA10RY BASIS EST. 00ST BV-2 POSITI N 14 Contairement simp data usirs draft Q480.26; SER OI 52 lbne We used a method acceptele to the Connission; MHtlU, SRP & Reg. Guide the curremly apgroved Reg. G.
15 Lightig & rh-nication/ diesel not IE Qf+30.68 mne over 1 million Our power sources are sufficiertly reli&le and no requirenent exists.
16 Requirmumt for Mech EQ Progran Q270.2 mne 150,000 Canmitted to the NtC to terfonn an EQ 1rogran for Mecharncal Equipmert.
17 Use of 002 in cable spreafirg area SER OI 9f+
App. R, Req's suppre-10 million +
00 meets intert of App. R.
2 sion only 6 nonth delay 18 Use of A9E Code in pipirg design does Q210.32 None BV-2 designed in a:cordance with 10CFR50.55(a) not guarartee safety fmetion will be ard A9E III.
fulfilled 19 Seismic EQ 10% margin between test Q271.6 Reg'd. for seisnic EQ Unknown; poten-BV-2 is 323.71 ami an adequate margin was response spectra ard req'd. response fran GDG btt rxt req'd. tially affects used, i.e., there is a margin of safety spectra for 10%
all BCP IQPF between test response and req'd. response spectra.
20 Cross-trainirs prqran for operators SER 13.2.1.2 PURIG 1021
! URIC 1021 has no basis in the SRP or the rquiat ions.
21 mbil pipeline explosion analyses Q311.5 through Ibne citsi
~
BVPS-2 has stown, in a cordance with Reg. @.
Q311.8 1.70 ani SRP 2.2.3, that an ecplosion is nct a design basis evert. No further analyses of effect of an explosion are regtdral.
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