ML20091H186
| ML20091H186 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/30/1984 |
| From: | Woolever E DUQUESNE LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-4-068, 2NRC-4-68, GL-84-08, GL-84-8, NUDOCS 8406050091 | |
| Download: ML20091H186 (2) | |
Text
O 7
2NRC-4-068 (412) 787 - 5141 Telecopy 6
Nuclear Construction Division May 30, 1984 Robinson P!aza, Building 2, Suite 210 Pittsburgh, PA 15205 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. Darrell G. Eisenhut, Director Division of Licensing Of fice of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Identification of Backfit Requirement Nunber 9 Gentlemen:
In Draf t SER Section 7.3.3.12 (attached), the NRC identified the concern that the steam generato r level control design did not meet the requirements of Paragraph 4.7 of IEEE 279.
Duquesne Light Company (DLC) responded to this,. con-cern in le t ter 2NRC-4-032 to G.
W.
Knighto n dated March 28, 19 84.
In the r es pons e, DLC explained that compliance with IEEE 279 is not required in this case because core pr ot ect io n is maint ained even if the very specific failures pos tulated by the NRC were to occur.
The NRC responded to this in-a letter frcan Mr. G.
W. Knighton to Mr. E. -J. Woolever dated May 5,1984, indicating that Dif would either need to modify the steam generator level control design to ecunply with IEEE-279 or need to provide an analysis showing that the cons eque ns es of feedwater addition are not safety significant.
The BVPS-2 PSAR describes the standard Westinghouse three channel design.
This document provides the basis for the issuance of the BVPS-2 cons truct ion permit.
Ad di tionally, despite the existence. of IEEE 279 since 19 71, nume rous operating Westinghouse PWR's have steam generator level systems similar to that provided for BVPS-2. _ Therefore, it appe ars that Mr.
Knigh ton's May 8, 19 84, letter transmits a new requirement without full implementation of NRR procedures based on-10CFR50.109; Generic Letter 84-08; and NRC Manual, Chapter 0514.
DLC requests that the proposed recjuirement be submitted to NRC management for approval, in accordance with the Of fice of Nuclear Reactor Regulation (NRR) procedure for management of plant specific backfitting, prior to transmittal as a licens ing requirement.
DUQUESNE LIGHT COMPANY By
/.
E.VJ. Woolever Vice President KAT/wjs At tachment ec:
Mr. H. R. Denton (w/ attachment)
Mr. G. W. Knighton, Chief (w/ attachment)
Ms. M. Ley, Project Manager (w/ attachment)
Mr. M. Licitra, Project Manager (w/ attachment)
Mr. G. Walton, NRC Resident Inspector (w/ attachment) p 8406050091 840530 PDR ADOCK 05000412 PDR E
a i
.i t
'i I
P.
i t!
i k) i
- l l
1 i
7.3.3.12 Staam Generator Level Control anc Protection l
n i
m d
j l
Three stea= generator level channels are used in a twc-cut-of-tnree logic for 1
isolatten of faccwatar on hign staam generatcr level.
One of the three level' h!
cnannels is used for control.
This design for actuation of feedwater isola-tion dcas not meet the requirements of Paragrapn 4.7 of IEEE 279, "Centrol ad
,1 p}
Protectica System Interaction," in that the failure of the level enannel used i
for cont ci could require arctactive action and tne remai9 der of tne ;rctacti:a
}
i system cnannels would not satisfy the single-f ailure criterion.
The a:plican:
)j.
nas not responced to this concern.
This is an open item.
]
t t.
}
[
7.2.2.12 II Sa W tin 50-05 Concerns j
n IE B letin 30-05 requests a review cf ali systems serving safety-re tad fe :-
L
- tions t ensure that no devica will change position solely becausp of the resu cf a ESF a atien signal.
The applicant was requested to respond to IE
- d Bulletin 80-0.
.s
]
1
?
The staff has review the applicant's responsa in F R Amendment 4 and fines '
that the applicant has r yiewed only the specific otential problems listed M]
.s
,l l IE Bulletin 80-06.
The int t of IE Bulletin
-05 and NRC cuestion 420.3 us stems to b reviewed.
This item is ocen unt 1
)r ]
to require all safety-related y\\
4 a complete response is provided by the plicant.
q 11; N
7.3.3.14 Incapandance Between Ma al an Autcmatic Actions The applicant's response to tE Bulletin 80-05 s
.es:
"All circuit y for c:: -
ponents actuated by an E~e actuation signal have,een cesignec sucn tnat tea
!j or signal cannot be erridcen manually or automat y wt ta an E5F actuati::
signal present.
component may be, reset by first resett'ng the ESF actuatic of signal and tner manually resetting ne component."
The staf*'s review of :,n
\\
d a
ij i
transfer fr tha control room to the ESP Ptvealed that safety 'njection s=:;
L!
cannot t s:cpped manually if SI is initiated after tne transfer.
- \\
/
Tr staff is concerned tnat, uncer accident concitions, as.e;; as n :ne cas l'
(
d i
<- m e te-t.uuucn2f._sa f ety_acucas._ neue.amuys:ney
- :-. {l e
4 d4 g-h e e A W,
-n,
,r..
...