ML20127L859
| ML20127L859 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/15/1984 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Rogers W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20127L745 | List: |
| References | |
| RTR-NUREG-0933, RTR-NUREG-933 GL-84-19, NUDOCS 8506280163 | |
| Download: ML20127L859 (4) | |
Text
, _ _ _.
e
-g u '
e OCT 1 5 1984 MEMORANDUM FOR:
K. G. Rogers, Senior Resident Inspectod, Davis-Besse FROM:
C. E. Norelius, Director, Division of Peactor Pro,iects SUPJECT:
DAVIS-BESSE - DIFFERING PROFESSIONAL OPINION The purpose of memorandum is to respond to your memorandum dated
~ July 24, 1984, Shafer regarding the powering of a vital bus from a non-Class IE power source. This matter was discussed between N. Jackiw and G. Holahan of NRR. This same concern was previously identified in a memorandum from C. Michaelson (AE00) to H. Denton (NPR) dated July 15, 1980.
This memorandum stated that without technical specification restrictions governing the Class 1E 120 VAC vital instrument buses and ass'ociated invertors, these power sources could be out of service indefinitely and thereby may place certain safety systems in a situation where they could not meet the single failure criterion.
NRR concurred with the AE0D recommendation that LCO's should be applied to these operating reactors not presently having LCO's specifically addressing the loss of Class 1E 120 V AC vital instrument
-buses.
The Division of Licensing (DL) has led the NRR effort to resolve this issue since it was identified by AE0D.
A technical evaluation by Lawrence Livermore National Laboratory, accepted by the NRC, dated October 28, 1982, supports a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> / year outage limit as a Limiting Condition for Operation, The lead responsibility for this issue (Generic Issue 48) has now been transferred from DL to DSI (Division of Systems Integration) by memorandum from T. Speis to P. Mattson dated March 1, 1984).
DSI's work of establishing an appropriate technical specification change is nearing completion, subject to NRP and CRGR review. is a schedule of completion for this generic issue and it will be monitored by the Generic issue Management Control System (GIMCS). The 120 V AC vital instrument bus issue was ranked by priority in accordance with the reouire-ments of NUREG-0933 and Generic Letter 84-19 (Attachment 2).
All other documen-tation relating to the proposed resolution of this issue will be sent to you upon your request.
There is no disagreement with the issue that you have raised.
The cuestion is related.to the timirg of implementing the change in the Technical Specifications.
I support the NRP schedule for providing a generic resolution to this issue.
However, in the interim, N. Jactiw has contacted the Davis Besse plant manage-ment and they tave agreed to comply with our ocsitier. cn the operability of the buses until this r+tt+ r is rese'.ead.
We were risc infcrmed + hat the 'icensee
~
est or this surject.
has submirtod a Tectnical h e:ifi;E'iet char 4e r e' 8506200163 9503C0' PDR ADOCK 05000346 P
PDH
[
I
~
s.
e t
G.. W. Itogers 2
0CT 1 5 1984 g
l Your concern in this matter is appreciated.
If you have any additional questions, e
please -feel free to contact me or your section. chief.
C. E. Norelius, Director Division of Reactor Projects Attachments: 'As: stated cc:
J. G. Keppler A. B. Davis
'D.Eisenhut, NER-G. Holohan, NRR R._L. Spessard
.f 1
El(CN 1
EII1 Rill M./Il.i S.lf1s M'T OecHW/bl SP{er
-10/11/P4 h,/
R I ' ' D,
~._
a., -
u p Q,l 1 N
~~
[
L m'
i GENERIC ISSUE MANAGEMENT CONTROL SYSTEM
. A.
Task Tac No Action Manacer Issue Office /Div/Br Issue Level Numb 7r h
ZT -
- 0. Chopra Safety /
Active-L1 NRR/DSI/PSB g r z z.3 48 Note 2 LCO for Class TE 120V AC Vital Instru=ent Buses in Titic Operating Reactors.
Memorandum to D. G. Eisenhut from H. R. Denton da Work Authorization --; Octcber 15, ISE3.
Memorandum to R. J. Mattson from T. S. Speis dated March 1 1984, " Transfer of Lead Responsibility for Generic l
. Issue No. 48 from DL to DSI "
NRR FY-84 Operating Plan, (Appendix G).
[
PWR 120V AC Vital Instrument Buses and Inverte Contract Title -
Specifications Centractor Name/
Lavrence Liver =cre Laboratory /UCID 19469 F I N N o. -- ---
Review LLNL Technical Evaluation Report containing theDeter=
technical finding to the above issue.
h taff or Work Scape ----- ---
any need for additional work to be performed by t e sPr After CRGR approval issue staff contractor.
h ical of the issue for CRGR review.
generic letter requesting all licensees to propose tec n l buses specifications limiting the ni=-the 120V AC vita 1E DC ray be energized free a source other than its Class bus and associated inverter.
A. im.
T e
Plant Technical Specifications vegi6i -a ;i-Af f ected Documents -- h t!.m. l 25.
Erx uuJc. -..: T M w.ii im M
et i.t c cf +k t.
tec p tsa 'y LLeJt.'\\tn Status U 19 M Pt E u a\\
- t. m.
gY c z. f g r j
~
~
MR None Prchle:/ Resolution. -
A-tual Technical Resciution -
Curren:
Cricinal 10/15/E3
_E_esteres Generic Issue t-E assiened te DL by Dire:ter, NER 03/01/64 Generi: issue lee: rescensicility C5I transfer frec DL ::
As of Thir: Ot.Erter FY-54 w__ _. _ _ _. _ _ _ _. -. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _. _ _ _. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _
1
_~ w -
u
' -4 d
7
- IM A -- '
L
' T-Generi'c Issue #48
'f i~
2-L
~
r 1-
["
Actual Curren_t Oricinal_
05/01/E4
_ Milestones-10/84
~
R: quest to RRAB for technical assistance to review' PRA done by LLHL 02/85 Complete review.of LLL report by the RRAB 04/85 Technical resolution identified.
Prepare review package for CRGR 06/85 Division Director approval of i
Package to other division directors for
~
CRGR package.
coments.
i-07/85 Other division corrents incorporated.
Package sent to Director, NRR.
08/85 Director, NRR review complete.
Fackage sent to CRGR.
' 09/85 CRGR review complete.
10/85 EDO approval.
01/85 OMS clearance.
02/86 Issue generic letter to all cperating plants 1
02/85 i
Technical resolution complete I
s
- Il@9 DATE:
N Y [Mp TASK 1% NAGER VERIFICATION:
f i
As c' Tnire -Quarter FY-54 l
}
l l
l l
i l
I l
C-n er >!
l
-t l
l
{
t '3 55 ;"x
.--ep!
~*
-..........u....................
~=aMAL RECCRD CC?Y- - - - -
gf-y.ct,r,vai m
-?,. '
l !v..
.g l g
u.
l~-
~~ f6
.h j~
UNITED STATES
[C l g3 j
f MG NUCLEAR REGULATORY COMMISSION N19
[,fl
[
f, f ' ',".r. ( ( h W ASHINGTON, D. C. 20555
/r h
o' August 6, 1984
_le.nilm i
m TD ALL LICENSEES OF OPERATING REACTORS, APPLICANTS F AND HOLDERS OF CONSTRUCTION FERMITS i
Gentlemen:
AVAILABILITY OF SUPPLEMENT 1 TO NUREG-0933, "A PRIORI GEhERIC SAFETY ISSUES" (Generic Letter No. 84-19)
SUBJECT:
This letter is to inform you that Supplement I to NUREG-0933, "AIss li or by writing the NRC/GPO Prioritization of Generic Safety (301) 492-9530 and may be purchased by callingSales Program, Division of Tech 20555, or the National Nuclear Regulatory Commission, Washington, D.C. Techni Springfield, VA 22161.
The Supplement presents the priority rankings for generic safety f
related to nuclear power plants.in the timely and efficient allocation of i
isk.
those safety issues that have a significant potential for reduc ng r The safety priority rankings of HIGH, MEDIUM, LOW, and DROP have bee i k to assigned on the basis of rist significance estimates, the ratio of r s ft costs and other impacts estimated to result if resolu d tion of the quantitative or qualitative f actors, as discussed in the Intro uc Al though To the extent practical, estimates 6re quantitative.
l changes to nuclear power plant designs or operation are assumed,
-report.
h impacts purpose in prioritizing the issues is to estimate costs and ot er that miaht result if such chances were implemented.
The priority rankirgs in the report are based on generic assessme Thus, the assessments of plants thought to be typical of a class of plants.
ific plant safety significance of _ an issue might be greater (or less) for a spec because of features of the design or operation that are different from assumed in the generic assessments.
(1) the issues that have been resolved since
- ublication of fd' REG-0933 ir, December 19E3; (2) the issues that Tne E.jpriement contairs
es with lor l recoved f ror further cor,siceraticr by the NRC (i.e., the HIGS cr MEMUM priority resolution (i.e., those issues nearly reschec or witt or raniings),
hDG
- 2 F~.
,.-m-.
v
.j
.g. 1
- :n s....
_ r a, c - '
=:
w This ' letter does. not contain any new requirements cr guidance for licensees of operatin; reactors, applicants for operating licenses, and holders of construction permits. - No reply is required.
1 c
d1t)
J.YN g f arrell G.(.E'lsenhit,(6irector D
g Division of Licensing-Office of Nuclear Reactor Regulation
~
E L
e UNITED STATES -
JUCLEAR REGULATORY COMMISSION
.g$,s$t s'e'It WASdlNGTON, D.C. 20s55 -
us==c aas= = t 088tCIAt SU$1NE$$_
....,' a. m
- tNALTT FOm ansvATE USE SYJO 160137006273 1 1151992G12G22 05 *.KC R t G I 5*.
Ill P:GIOlaL A D *'1.41514 A T OP 7 99 84 '10 5 E V E L T R L' GLE.~~ttYi IL 60127 r
p e
9 m
,_,,-~-,,-~.-,-ee+.
-