ML19305D107
| ML19305D107 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/03/1980 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-01B, IEB-79-1B, NUDOCS 8004140064 | |
| Download: ML19305D107 (3) | |
Text
Ih PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 SHIELDS L. DALTROFF naErm'ic'"enNchore March 3, 1980 Re: Docket Nos. 50-277 50-278 IE Bulletin 79-01B Mr. B oy ce 'H. Grier, Director Region I Office of Inspection & Enforcement US Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
This letter is in response to IE Bulletin 79-01B, forwarded to us on January 14, 1980, concerning environmental qualification of Class IE equipnent.
The " Action to be Taken by Licensees" and our responses are treated sequentially.
Action to be Taken by Licensee 1.
Provide a " master list" of all Engineered Safety Feature Systems (Plant Protection Systems) required to function under p os tulated accident conditions.
Accident conditions are defined as the LOCA/HELB inside containment, and HELB outside containment.
For each system within (including cables, EPA's terminal blocks, etc.) the master list identif y each Clas s IE electrical equipment item that is required to function under accident conditions.
Pages 1 and 2 of Attachment 2 are standard f ormats to be used f or the
" master list" with typical inf ormation included.
Electrical equipment items, which are components of systems listed in Appendix A of Attachment 4, which are assumed to operate in the FSAR saf ety analysis and are relied on to mitigate design basis events are considered within the s cope 8 0 0 414 0%Y L
O
=
Mr. Boyce H.
Grier Page 2 i
of this Bulletin, regardless whether or not they were classified as part of the engineered safety features when the plant was originally licensed to operate.
The necessity l
for further upgrading of nonsafety related plant systems will be dependent on the outcome of the licensees and the i
NRC reviews subsequent to TMI/ 2.
f
RESPONSE
I i
A master list of all Engineered Saf ety Feature Systems required j
t o innetion under the des cribed p os tulated accident conditions is l
provided in Section I of Attachment A.
For each system within t h'e master list, each Unit 2& 3 Class IE equipment item that is required t o f unction under the described p os tulated accident i
conditions is provided according to the standard format.
The scope of the Electrical Power System includes wiring materials, j
and the use of the identified wiring materials is applicable to j
all other systems.
The plant emergency procedures which apply to the des cribed p ostulated accident conditions have been reviewed.
Unit 2 and 3 equipment, which is located in a hazardous environmental area and is not Class IE but is assumed to operate
{
in the emergency procedures, is identified in Section II of j
Attachment A.
I 2.
For each class IE electrical equipment item identified in l
Item 1, provide written evidence of its environmental l
qualfication to support the capability of the item to function under p os tulated accident conditions.
For those class IE electrical equipment items not having adequate l
qualification data available, identify your plans for l
determining qualifications of these items and y our s chedule l
for complacing this action.
Provide this in the format of.
RESPONSE
The written evidence of environmental qualification f or each I
identified Unit 2 Class IE equipment item is included in Section I of Attachment A.
The written evidence including the plans for i
res olving qualification documentation deficiencies is provided in l
the requested format except that Notes and References are provided as a subsection of Section I and are applicable to all f
systems.
The Unit 3 equipment is identical to the Unit 2
(
l equipment in most cases; however, due to the volume of work l
required for the 45-day response a specific review for the Unit 3 equipment has not been completed.
It will be completed and included in the-90-day response t o this Bulletin.
i 3.
For equipment identified in Items 1 and 2 provide service condition profiles (i.e.,
temperature, pressure, etc., as a
-n
o Mr. Boyco H. Grior Pcgo 3 function of time).
These data sh ould be provided f or design basis accident conditions and qualification tests perf ormed.
This data may be p rovided in p rofile or tabular f orm.
RESPONSE
A preliminary HELB accident analysis for outside primary containment has been comp leted, however, a review of the analysis has revealed that the approach was overly conservative.
In order to establish realistic HELE accident environmental conditions a re-analysis has been undertaken and is scheduled f or completion by April 10, 1980.
The HELB accident service conditions will be submitted within 30 days af ter completion of the re-ana ly sis in order to provide our engineering dep artment adequate time to review the p rofiles.
The LOCA profile for inside primary containment and the Class IE equipment qualification test profiles / tabulations are included in the Notes and References, subsection of Attachment A,Section I.
Very truly_ y ou rs.
/
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/__.
y Attachment
/ ' El{ bl'l l
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cc:
Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 9