ML19242A335
| ML19242A335 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/13/1979 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7908010432 | |
| Download: ML19242A335 (11) | |
Text
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PHILAD ELPHI A ELECTRIC COM PANY 2301 M ARKET STREET P.O. EOX 8699 PHILADELPHI A. PA.19101 SHIELOS L. DALTROFF ELECTRIC PH UCTION June 13, 1979 Docket Nos.:
50-277 50-278 IE Bulletia 79-01 Mr. Boyce H.
Grier, Director Office of Inspection & Enforcement Region I United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
This letter is in response to IE Bulletin 79-01, forwarded to us on February 8, 1979, concerning the environmental qualification of safety-related electrical equipment.
Because of the unavailability of information from manufseturers, we have been unable to furnish all the requested documentation within the 120 days required by your Bulletin.
We are continuiny to gather the necessary documentation as expeditiously as possible.
Submittal of the completed work is anticipnted by October 15, 1979.
The " Action to be Taken by Licensees" and our responses are treated sequentially.
Action to be Taken by Licensee 1.
C omp le t e the re-review progran described in IE Circular 78-08 within 120 days of receipt of this Bulletin.
Response
The re-review of safety-related equipment installed in primary containmcat has been completed with the exception of motor operated valve actuators.
Limitorque Corporation has agreed to provide the applicable qualification information based on the equipment serial numbers and purchase order numbers.
This information was provided t) Limitorque for Unit 2 valve actuators by letter dated 5/17/79.
The Unit 3 Limitorque serial numbers will be obtained during the current Unit 3 outage.
This
///.
cgo 195 2008010 G
Mr. Boyce H.
Grier Page 2 information along with purchase order numbers will then be sent to Limitorque.
The re-review of safety-related equipment installed outside primary containment has been initiate!, and the following activities describe
,u t T. orts to date:
(1) A review of the Peach Bottom APS FSAR Supplement 2 (High Energy Line Break (EELB) Analysis) has been completed.
This analysis provides the basis for outside containment qualification review.
The accident conditions are identified and the system operations required to respond to the accident are identified.
(2) A tabulation of all safety-related electrical equipment located in the reactor building is in progress.
(3) General Electric Company is searching their file for qualification documentation for NSSS supplied equipment.
(4) Availab]e heat transfer studies have been reses ched to determine their applicability to the accidents identified in the HELB analysis.
Completion of the re-review for the safety-related equipment l o c a. t e d outside primary conts'nment is contingent on an analyisis to determine the values of the environmental para ceters resulting from each of the identified HELB accidents.
Completion of the environmental analysis is anticipated to be early August 1979, and the re-review of equipment qualification is anticipated to be completed by October 15, 1979.
2.
Determine if the types of sten mounted limit switches described above are being u3ed or planned for use on safety-related /alves which are le aa t ed inside containment at your facility.
If so, provide written report to the NRC within the time frame specified td to the address specified in Item 4 below.
Response
The Main Steam Isolation Valve limit switches asociated with the reactor protection systeru,' R P S ) perform no safety function during or following a LOCA.
They do perform a safety function for a Steam Line Break outside of containment and are qualified to perform their safety function by virtue of GE tests.
NAMCO limit switches (EA-700-86010) which are very similar to those used on the Peach Bottom APS - Main Steam Line Isolation Valves (EA-700-50100/SL3CB2-N) were tested by General Electric Company in the LOCA and post LOCA environments.
G.E.
Co. Plant and Equipment Engineering Memorandum No.
126-43 documents the results COC
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u
Mr. Boyce H.
Grier Page 3 of these tests; the switches are capable of operation for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a LOCA.
The Main Steam Isolation Valve limit switches associated with the control room indication are not considered safety-related equipment and, therefore, Peach Bottom APS indication circuits were not designed for post cident monitoring.
3.
Provide written evidence of the qualification of electrical equipment required to function under accident conditions.
This written evidence should include:
- 1) component descrintion; 2) description of the accident environment; 3) the cavirenment to which the component or equi,, ment is qualified; 4) the manner of qualification which should include test methods such as sequential, synergistic, etc.
and 5) identification of the specific supporting qualification documentstion.
"'r those items not having complete qualification data ava.lable for review, identify your plans for determining qualification, either by testing or engineering analysis, or combination of these, or by replacement with qualified equipment.
Include your schedule for completing these actions and your justification for continued operation.
Submit this informatior to the Director, Division of Reactor Operations Inspection, Office of Inspection and Enforcement, Nuclear Regulatory Commission, Washington, D.C.
20555 with a copy to the alpropriate NRC Regional Office within 120 days of receipt of this Bulletin.
Response
The attached summary sheets provide the written evidence of the qualification for safety-related electrical equipment located in the primary containment Additional sheets for safety-related electrical equipment outsic? of the containment will be assembled and submitted after review or the environmental parameters as described in answer to Item 1.
It is anticipated that the re-review for outside containment equipment can be completed by October 15, 1979.
Re-review of safety-related equipment installed in primary containment has been completed with the exception of confirmation of existing data for Limitorque motor operated valves, and no unqualified equipment has been found.
Additionally, Supplement No. 2 to the Final Safety Analysis Report (FSAR) for Peach Bottom Atomic Power Station Units No. 2 & 3 contains information concerning the protection provided against effects of high energy piping systems failure outside the primary containment, and the protection of safeguard ecciement from the direct and environmental effects of the postulated pipe failure.
The fact that no safety-related equipment has been identified that is not e
s
Mr. Boyce H.
Grier Page 4 qualified for its intended service coupled with the fact that the aforementioned qualification program is in progress, provides justification for continued operation.
4.
Report any items which are identified as not meeting qualification requirements for service intended to the Director, Division of Operating Reactors, Office of Nuclear Reactor Regulation, Nuclear Regulatory Commission, Washington, D.C.
20555 with a copy to the appropriate NRC Regional Office within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of identification.
If plant operation is to continue following identification, provide justificatior. for such operation.
Provide a detailed written report within 14 days of identification to NRR, with a copy to the appropriate NRC kegional Office.
Response
To date, we have not identified any safety-related equipment which is not qualified for its intended service.
Very t r,u ly, y o u r s,
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Attachment cc:
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Nuclear Regulatory Commission Office of Inspection / Enrorcement Divisions of Reactor Operations Inspection Washington, DC 20555
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EfiVIRONMENI (LOCAT10N) er1:rary co n t., i r..
IINE QUAL.
DOC.
_ID N
.t QUIPilENT CE5LRIPfl0N RE Q ' D-PARAMETER SPEC.
QUAL.
ME Trf 00
- REF**
REMARKS 1
l/O ?/3-02-13 la %c INA t K IB T** air optrated velv2 !s Ne t re. Lwp s tm:.ple Temp. ( f)
Ng.
!., DGd Analysis 1, P, Q ussi to 1 s al ut e r-e s Lir< isolati<- ve l y-Press- (psia)
Letter f resn wa ter sun.ple fror. loop b.
J>' cat y d 300 ilU 120 I'0I ULQ-G. D. Edwards a
- volt, O %rt:
Radiation j _. _ _._
g 4.,n Chem.
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_2 AO 2/,3:02-116 WA&ELB R.e air -operated vSlve is Mair Steam 'vple Li r.e ICmp. ( f)
Aug, 4, 1[r78 Ar.al si s 1
- 2. A 3.
us e d t o i sola t e c.a i r. s t eam f
=
!;olas t ica '/alv-:
press. (pSid) pg m.-
Rel. Hura-sa.Tple line c:. re actor ver.sel G. D. Edwards l ow wster level
- S" cat. y rb300c61U Radiation to Anco a
l ?O 'Jol t, 60 N rt ;
Chen.
3 Wi ri " Ir e t r. ads USUddb u ::.s o tm 5:rnirsl f l oc.s s T en4>. ( F) 320*F 1, L &5 "h Termir.sl ? locks are
.a PH100 Serie.s Ifd Nc.
EfCSS- (PIIO)
_ __lgh h.1.f E2Lt2.ngly power and
'% rst na, Te rmir.a1 ' locks Rel. Hum.
cg o,y c a..t rol to W re s.u a r d Eg n ic a r.1 Ir 00 Se es Radiation
- y p6 g.<
4 Chem.
4 00ck; ctos Calle i?d sec.
LOCA & W LS The catle is toed to cupplf Fi t'"wa l l III NT,._. _O _ _
__ )MP
__. ML
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._ powe r c 'd cor.t rol ' o sa fegu a rd P retrol III
_ Press. (psia)
_"1 Psig n
f,el. Hum.
A-10M
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c_.,__,
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kadiation them.
This list a compila tion o f i ten-s t,y componen t.
Do not list the same type of component more than once.
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IT!H FQUIPMENT DESCRIPTION 1(Q'D.
PARAMETER SPEC.
QUAL.
fqE TIIOD
- REF" RE!1 ARKS 5
Prvw :11 Pe.e t ra t t ora 101 ra y s LOCA & FCLb The A rety function is to 3.E. Co. (Low Voltage Temp. ( F) 340"y Test 1,7,8, & 9 naintain Dr ell ir.tegrity Press. (psla)
Jap r.v t ml )
Rel" Hun' 3g
- p31, du r i n.1 nera.a1 and_durir.g 2.-
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Radiation u Ma ar.d pos t desi gn tasi s ever.t.
Chem.
_LLalhtim;cra r_ _;a.e t.r.a t io ns are ur.e1 to s gply powe r ar.d Temp. (UF) control to safecard egitpment.
Press. (psia)
Rel. Ilum.
Radiation Chem.
O Dr /wfll b; _ t ra ti ons 101 days LOCA & PCLB The safety (2nction is to.
Tenp. ( F) 281 F Tt t 1, d, & 10 u.aintain dryvell integrity n.y t e1,1. ci.m..c-.
Ca rp. ( Hig@l t a e)
Press. (psla)
F.? psig
_ derir.c n o r ma_1_ a r.d d u r i n g a Fel. INm.
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Test & Analy:.s desi.;n tesis eve _nt.
Chem.
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a LNA ar.d/or ?CLS Rel. Ilum.
eve: t 8
Radiation Chem.
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I This lis t is a c";rpilation o f items by conponent. Do not list the sam type of component more than once.
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EtiVIRONMENT (LOCATION) I>riury cor.tain.
TIME QUAL.
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__ EQUIPMENT DESCRIPT!C1 RfQ'D-PAR /J1E T E R SPEC.
QUAL.
MtIHOD*
REF**
R EltARV.S 8
2 /3-02-05 A a r.d 6'A f 50 rec.
I.3CA & !CLb Valves close on desien basis Temp. ( F) 2Lo y Test ig jj e ver. t to isolate loops.
Limitorque motor opurited press- (PSI 3) 105 Psig Investigation is cor.tir.cing.
valve recire, sy s t rr. p q _
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< r0- 100I.
crors tie valves t on pog yg Chem.
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2/3-0?-53A ar.d ';38
{ 80 sec.
LOCA i FELB valves close or d sign Limitorgge tutor Icirp. (07)
Opu rit:d valve Press. (psia)
__31.0 F
. Te s t. _ _.
1 1 11 Nsis ever.t to isolate recire.
105 Psi.:
loops.
Ir.vestigation is n
S" -3 llel. Hum.
90-1001 c or.t i n ai r.g.
Fec t re. Loops A ar.d D Radiation pga r.g
__P w pJ rc% rv Val ves Chem.
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. 2/hC2 '.l' v.lsD G"'-
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- Temp. (UF) 340 F Test 1 g 11 velves close or, design t+ sis A,aW1 Vol '.
EfUSS- (PSid) 105 Psig event to isolate loops.
-00 Rel. Ilum.
00-1001
Ir. vest qation is contir.vir..;.
stm Pmy Ridiation ciro.
200 pa Di s cr a r.'
Cross tie epssa Chem.
11 P/3 10-18 6 60 sue.
LOCA & McLb Valve isolates h!B reactor Limitorque Motor operated,
Temp. (c )
340 F
'l es t 1 & 11 F
shutdown coalir.g supply line valve Pre.s s. (psia) 105 Psi.e on isolation sig:.al.
h-150, Rira Rel. llum.
%-100(
Investiestior. i s co:.tir:uing.
L.atd,w:. ccoli rs ludi a ti on 200 F5 I:.olution Valve Chem.
This lis t is a conpilation of itens by component. Do not list the same type of component more than once.
- ie, separate ef fects, sequential, etc.
!:.c : rn tinq onviron ont whe re m re than ene applies
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ENVIRONMENT (LOCATION)
TIME QUAL.
00C.
ITfil E0blPMENT DESCRIPT!CN REQ'D.
PARAMETER SPEC.
QUAL.
METiiOD*
REf**
REhARKS 19 _.p/].93-15 i MO r.ec.
LOCA & ICLB Valve isolates U dI tartire r4-4 t m," " >t.'r Temp. ( F) 340 Test 1 & 11 stea4 supply on r.on-failsafe Oru r:.ted Valves ress. (psia) 105 paig isolation sigr.al.
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90_1001 Ir.vestigation is contir.uir.g.
Radiation
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Chem.
.I glqt.io Valve 13 P/3-13-15 90 sec.
LocA & FCLB Valve isolates hCIC Temp. (Of)
%0D lest 1 & 11 Turcine Stes:r L gply Line 1 L _. m m.,... s., + n..
pp.:.r i+d nives Press. (psia) 105 1: i g on non-fallsafe sier.al.
Df:%O00-5, RCIC Rel. Ilum.
m -LOO, Ir.ver.tiptica is cor. tint.ind St.e Li ne Eddl0liOR 000 F9 i tus %
Isolation Valvu Chem.
14 2/3-12-15 U:0 see.
___._ULL LOCA & I Valve Isolates EWCU Li r.i t org m Mato r l etcp. ( f) 340 F
'I e s t 1 i_.11 __ _ Lum or.
s lation Gigr.al.
0;rratel Valves l'ress. (psia) 105 Psi g Ir.vestigation is car.tinuing.
% 10, Eeactor Rel. Hum.
00_100%
a Uate t:leanup Inlet Radial 10n 200 !.m a
Isclatica Valve Chem.
1S 2/3-02 74 5 N Sec.
LOCA & ItJLB lust Valve Isolat as f'.ain Lirnitorque Motor Valves Temp. ( F)
%0 F 1 & 11 Steam Lir.e
_' rain on i
SMB-000-5.
Idoa r d Press. (psia) 105 Psig Isclation t ig '.al.
Bir Cte r Line Frala Hel, llum.90-104 Investivat:in is contir.uing.
__I c o i a t i n a Vsive Padiation w py (hem.
This lis t is a corpilation of i ter.:s by component. Do not list the same type of component more than once.
- ie, separate effects sequenti il, etc.
- Please attach typed lists of n feience d.icuxnt s U
'imiti m on/ir:er
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ENVIRONf1ENT (LOCATION) Primary contain.
TIME QUAL.
00C.
I TLt.
_ EQUIPMENT DESCRIP W REQ'D.
PARAMETER SPEC.
QUAL.
METHOD
- REF**
REMARKS 16 2 /
-0.' 43A & 4'3 B
{ti0 Cec.
3 LOCA & FCLb valv:s close on desie:n tssis Iimitorgo Mator Ien0 ( f)
%0 F Test 1 & 11 event to isolate recire.
Opented valve
'rc S S. (psla) a g c,9 p 3 g,,
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r e i <,
IC I IIUU-
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c or.t i n ai r.
loeps A and S Pwnp l
R1diation r__
200 bm siction valv.
(hem.
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Rel. Ilum.
Radiation Chem.
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Re1. Ilum.
RadiatIcn i
Chem.
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Rel. Ilum.
Radiation Ch e n..
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This list is a corpilation of itenn by component. Do not list the sane type of corponent more than once.
- ie, separate ef fects sequential, etc.
Uw i i ni t i n a e n vi ri" mn t W re irr, ra than one applies.
- Please attach typed $1sts of refeirm e dmm.mt.
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\\t g3m f k * ' < (1 c d [; i $ ? M si d h E I1 PL ANT WJ!E:
Fesch futtom Unit 42 and // 3 Cm
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Et<VIR0 tit: Erit (LOCATION) Prie.ary Cor.tain.
Tit 1E QUAL.
00C.
ITU; EQUf FMENT DESCRIPTION REQ'O.
QUAL.
?!ETHOD*
REF**
REftARKS
_17 A0-2/3 02-dOA, MB, 110 0 LGPA % ?.C LH Solel.oi ds d_e,-er.e rgi te _ to
.1 Pa n
.ir m,-
Igno Iemp. ( F) 3!.0 F
'i e s t
- 1. 2 % 13 isolate rain steam lines on Press. (psia) 110 Psi,i isolstion sicr. sis, i rl s+ 1 r valvt air
- cperated c.ani fold.
I?el. Hum.
g,g Radiation f,+hj Ma r. f, - + o r r.1 by a.st mnti, Chem.
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valv-carp.
JS.
!_3'Z S h nMJf.
? C t-LOCA 1 1-CLb Preve:.ts overpressurization of Temp. ( F) 3to p hst 112 t!.e ILelear System. In o
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.T, y,
.e, T.
r.w n c t o r s t e a-. P-l i - f Press. (psia) 65 rst r additior., t!.e ALs future of val.,s, A.V.P. r #.M0 Rel. Hum.
m_ g tr.e
- n. clear sys. press.
Radiallon 3hhj relief sys, acts ir. car.junctior u.,n m :j rm Ch
- em.
with core s t.a._.dt y coolig sys.
.ol.m a t.i s for refloM ir.
t!.e core Teap. (UF) fa n ewir. small treds in t:.e Press. (psia)
, u. clear system process tar rier Rel. Hum.
Radiaticn Chem.
19 Cat >1e/cour.ector assemblies,
':te car.2.ectors are used to Pjle - a t i onal Co.
Temp. ( F) 3:.o p
- :st i, le s t.p ply power and car. trol to P-A.207!."4 F?a thru Pess. (psia) 105 I s i.i sa fe.r ard eg. ipa.ent
_____4 E-A-207!>03 In Rel. Hum.90-10X I
l Iladi a ticn 200 MH Chem.
s lis t is a cc-pilation of i te.~.s by CCmponent. C0 not list thc sare typc of corp 0nent nare than once.
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REFERENCES 1.
RES 5-3 (Qualification Drywell Equipment.)
2.
G.E. Co. Cover Letter G-HE-8-198 3.
ASCO Letter 3/17/78 4.
Franklin Institute Test Report F-C5022-1 5.
Franklin Institute Test Report for PECO FC5022-2 6.
Franklin Institute Test Report for P.E. Co. F-C2750 7.
C.E. Co. Cover Letter G-HE-8-153 8.
Vendor Print #6280-E106-213-1 9.
G.E. Co. cover letter G-HE-8-54 10.
Vendor Print #6230-E40-124-2 11.
Franklin Institute Test Report for Limitorque Corp. FC3441 12.
Franklin Institute Test Report for Pyle-National Company F-C3451 13.
G.E. Co. cover letter C-HE-7-154 (FDI-123)
AS : WJB : keh 5/29/79
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