ML19242B129
| ML19242B129 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/15/1979 |
| From: | Miller D PORTLAND GENERAL ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| TAC-11299, NUDOCS 7908070552 | |
| Download: ML19242B129 (13) | |
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.a Nu, June 15, 1979 Trojan Nuclear Plant Docket 50-344 1.icense NPF-1 Mr. R. H. Engelken, Director U.S. Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plaza 1990 N. California 31vd.
Walnut Creek, California 94596
Dear Sir:
Attached please find (Attachment 1) the supplemental submittal referred to in our letter of June 12, 1979, which transmitted our response to NRC 1E Bulletin 79-01.
As requested at the PCE/ Westinghouse /NRC meeting in Washington, D. C. on June 8, 1979, the intent of this supplement is to provide additional information documenting discussions on the capabilities of the presently installed in-Containment instrunentation to perform short-tera trip and long-ters nonitoring f unctions and means of backup long-tera tonitoring.
In addition, please note that we have discovered the following typographical errors in the June 12 submittal that require your attention:
Itea Reference Description 1,
Paragraph begins with:
"Ea,ed on the above, Lasi Pa rag ra ph,
we have concluded that proper documentation Page 5 exists to assume that the safety-related electrical equipment will function...."
The typographical error is with the word "a s sume".
Please revise this to read:
" Based on the above, we have concluded that proper documentation exists to assure that the safety-related electrical equipment will function...."
A corrected version of Page 5 is attached (Attachment 2).
2,
The column heading for pressure qualifica-All Pages tion is given as:
VENDOR PRESSURE (PSIA) read :5 41 1Gn 1
iJU Please revise this to VENDOR Pi',ESSU^
s'<.)
7 9080 0 E C 7
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Pert!ar.d Geceml Electric Ocmparr/
tir. R. II. Engelken June 15, 1979 Page two Item Reference Description 3
Att -chment 3, Arrows indicating common qualification Pages 3 and 7 references were inadvertently omitted from these pages.
Corrected versions are attached (Attachments 3 and 4).
Please contact Mr. C. Goodwin, Jr., Assistant Vice President, Thermal Plant Operation and Maintenance, if you have any questions concerning this supplementary submittal.
Sincerely, Q:Ahn
$64
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D. R. Miller Assistant Vice President System Engineering-Construction DRM/ilEW/SML/4kk3B18 Attachments c:
Mr. Lynn Frank, Director State cf Oregon Department of Energy 541 151 q >. ' L:
Attachneet No. 1 Supplement to IE Bulletin No. 79-01 Subnittal IN-CONTAIN!!LNT INSTRUllENTATION -
SHORT-TER!! TRIP /LO::C-TER!! !!ONITORING I.
SHORT-TER!i TRIP CAPABILITY The only in-Containment sensors and devices required to function for post-LOCA initiation of the safety-injection systen are:
(a) pressurizer pressure, (b) reactor coolant systen RTDs (Tavg), and (c) stean line flows.
Attachment No. 3 to the Portland General Elect ric Company's submittal dated June 12, 1979, responding to NRC IE Bulletin No. 79-01, documents the qualification of these instronents for operation in a post-LOCA environnent.
Attached Table No. I provides additional infornation concerning this qualification.
A review of the Trojan FSAR Chapter 15 ( Accident Analyses) indicates that a naxinun cf 35 see is expeceed before reaching a safety-injection signal setpaint in the pe',culated accident situation involving the slowest signal tise tinc.
Since the mininun instrument operability tine is at least I ninate (per Table 1). the Trojan plaat is assured of short-tice trip capability for these in-Containment devices.
II.
LONG-TER'I ' 0NITORING CAPABILl]
The inside Containnent instrumentation available to provide operational information or saf ety-injection initiation or both, that can provide l
post-accident nonitoring capability is as follows *
(A) Pressurizer wi.er level signal transnitter (three total)
(3) Steam generator water level signal transmitter (three per stean generator)
(C) RCS wide-range pressure signal transmitter (two total)
(D) RCS Tcold or Thot RTDs (one Thot and one Tcold per loop)
Attached Table No. 2, based on Attachuent No. 3 to the 79-01 bulletin submittal, provides additional information concerning the long-tern nonitoring capability of these instcunents.
The stenn generator water level transnitters and RCS pressure (wide-range) transa tters are located at the 48 ft ele va t ion in the Contain-t nent or about. ft below the taxinun water level that would result from a conditiot. III or IV LOCA break.
Estinated instrument subnergence would occur within about 3 hr for a 1 in. break, I hr for a 2 in.
break and lesser tae for larger breaks.
These instruments are pressure tight, but subne r),e n ce testing has not been conducted and the instruments may not provide mosttoring capability when subnerged.
The signal transmitters (Iten, A.
E and C) will be replaced at the ea rli es t 1 He crence Trojar c i.1 r Plant aYi, 7. r ml 1.5-2.
r.g;p
Page Tuo opportunity, upon acceptance of the Westinghouse qualification testing of Earton Models 763 and 764 by the NRC.
These acdels will be qualified for long-tern post-accident environnent nonitoring capability, including submergence, as part of the Uestinghouse Supplemental Qualification Prograa.
In addition to the above instrumentation, outside-Containnent instrumentation (or alternative inside-Containment instrumentation) is presently available for long-tern monitoring in the event of an accident.
ih's instrumentation acts to back up the existing ins trumentation for lonp-tern conitoring and is considered an interia nethod of achiev-ing reliable long-term post-accident conitoring.
Once the Barton Model 763 and 764 transnitters are installed, following NRC approval of the Westinghouse Qualification Program, this instrumentation will not be necessary or relied upon to achieve reliable long-tera nonitoring (although cost
-f it is ess ential to plant operatien and/or saf eguards initiation and will still be available).
This backup instrumentation, the function that it backs tg, and the way in which it can b; used to perform that function are as follows:
3ACKUP PRESENTLY FUNCTION INSTR OEPATION 1 IN3TALLED? USE OF B!CKUP INSTRUMENTATION (A) Pressurizer (1) Differential No Read directly from renote Water Level pressure indication.
PCE is presently r.easured outside in the process of adding a Containment dif. tential pressure trans-nitt atilizing existing presourizer sample lines located outside Containment.
If operation of the instrumen-tation is tested and found successful, specific test procedures (and operating procedures required in the event of an accident requir-ing long-tera nonitoring) ca n be made available before comaercial operation is resumed, but are not avail-able at this da t e (6/15/79).
(2) Pressurizer Yes By use of pressurizer tempera-steaa tenpera-(Sone ture indication from existing ture and water nodifica-pressurizer RTDs, a comparison tenperature tion of pressurizer steam and water RTDs required) tempe ra tu re s can be nade by the operator.,If the water tenperature io approaching the
..i s t ed in or h prefere; m 541 153
.<v.
gr,e Three BACKUP PRESENTLY FUNCTIO:I INS fRl"lENTATION I INSTALLED?
USE OF BACKUP INSTRU:!ENTATION stcan temperature, the pres-surizer nay be empty.
Ilow-ever, if the steam temperature is approaching the water teap-erature, then the pressurizer is going solid.
[ NOTE The existing pressuri-zer RTDs contain teflon-insulated lead wires and nay not be satisfactorily noisture tight for the post-LOCA environment.
The operability of these RTDs in such an environment will be enhanced by a nodification to the RTD wiring and encapsulation of the terminals with a high tenperature scaling compound.
This work will be completed prior to plant operation.]
(3) RCS pressure es (see Read RCS pressure directly.
v ar.d charging Itea C)
The reactor coolant systen is pump flow going solid if RCS pressure is rapidly increasing at the same tine that the charging flow decreases.
(4) RCP ataeter Yes Read anneter directly. A fluctuating or low reactor coolant paap ammeter reading indicates approach of two-phase (steam / water nixture) flow.
(5) Nuclear Yes Read directly.
An increasing Instrumentation c( ' Int rate indicates a decrease in shielding as water level approaches core.
(B) Stena (1) Differential No Read directly f rom remote Generator pressure indication.
PCE is presently Water Level neasured outside in the process of adding Containment signal t ra nsmi t te rs for each stean generator ut ili zing the 54i 154 i.i s t ed
- arr ot ar
Page Four BACKUP PRESENTLY FUNCTION INSTRUME NTATIO'i I
_ INSTALLED? USE OF BACKUP INSTRUMENTATION existing steam generator blow-down lines and main steaa lines located outside Containment.
If operation of the instrumen-tation is tested and found successful, specific test pro-cedures (and operating pro-cedures required in the event of an accident requirind long-tern nonitoring) can be made available before comnercial operation is resumed, but are not availatle at this date (6/15/79).
(2) Steam generator Yes Read pressure directly.
pressure (a) The atmospheric relief va lve can be periodically opened.
If the stean genera-tor is nearly dry, it will rapidly denressurize.
(b) Uhile using the condenser stean dump valves, the operator can listen for flow through the dump valve and confirn that the stean generator pre s sure is stable near the no load value.
(3) RCS Loop Thot Yes Safe shutdown conditions and Tcold should show an RCS loop AT (ie, Thot - Teold) less than full load AT.
Steam generator level has predict-able ef f ects on RCS loop A T cha ra c te ris tic s.
(4) Fill stean Yes This cethod would be considered generator solid a last re s or t.
Indication is (a) vater flow in steam lines and (b) possible discharge of two phase ':ater through atnos-phe r i c duop talven.
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Page Five BACKUP PRESENTLY INSTRU:!ET:TATION I INSTALLED? USE OF BACKUP INSTRU:!ENTATION FUNCTION (C) Reactor (1) Centrifugal Yes Charging puap discharge Coolant charging puap pressure is available from Systen (high pressure) panel C12 in the control room Pressure discharge and from the plant computer.
pressure (2) Centrifugal Yes Charging ptap flow is avail-charging pump able at panel C12 in the flow control room and from the plant c oup u te r.
Uith the charging pump running, the ptap curve can be exanined to estinate discharge pressure.
(3) Safety Yes Safety injection pump dis-injection charge pressure is available pucp (inter-at panel C19 in the control rediate pres-roon.
This pressure is only sure) discharge accurate after the flow pressure starts.
If there is no safety injection flow, this indicates that the RCS pres-sure is greater than the safety injection pump dis-charge pressure.
(4) RHR puup (low Yes RHR pump discharge pressure pressure) dis-is available at panels C12 charge pressure and Cl3 in the control roon and from the plant computer.
This pressure is only accurate af ter flow starts.
If there is no flow, this indicates that the RCS pressure is greater than the RHR puup discharge pressure.
(5) Pressure Yes Manipulate sample valves as indicators in necessary and read locally at various RCS the sample stations.
saaple lines (D) RCS loops Steam generator Yes Calculate RCS temperature by
- Tcold, pressure use of stean table.
Thnti incore th. rmo-54i i56 I l.i s t e U'
of preferi
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Page Six III.
CO::CLUSION Based on the above information, we feel assured that the in-Containnent instrumentation is adequately qualified as stated in the Trojan 1;uclear Plant FSAR for the short-tern task of initiating safety injection in a post-LOCA environment.
Lcng-tera post accident monitoring will be improved when the Barton Model 763 and 764 transaitters are installed.
lloweve r, the backup conitoring nethods available as described above, and the procedures for their use, provide adequate long-tern monitoring should the need arise.
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TABLE NO. 1 IN-CONTAINMENT INSTRU:!I:NTATION FOR S110RT-TER:1 TRIPS Trojan Nuclear Plant Inst rument Qualification Qualified Tiue for Description Numbers Itake & Model Reference Post-LOCA Operability Pressurizer Pressure PT455 Ba rt on similarity to
> 1 minute Transmitter PT456 Model 3')3 Itodel 386 PT457 1;C A!'- 7 / 44
'teactor Coolant TE413 A & B Rosenount Qualified by 14 days Systen RTDs TE423 A & B Model 170KS type test in TE433 A & B WCAP-9157 TE443 A & B Stean Cencrator FTS12 FT513 Ba rt on Franklin Institute
> 1 ninute Steam flow FT522 FT523 Model 384 Research Lab Report FT532 FT533 C-2623 FT542 FT543 tn b
Ui CO xT e/3rg8A12 h;
TABLE No. 2 IN-CONTAIN:1ENT INSTRUMENTATION USEFUL FOR LO'!G-TEPJi MONITORING Trojan Nuclear Plant Instrument Qualification Qualified Time for Cepable of Long-Description Nunbers Make & Model Reference Post-LOCA Operability Tern Monitorin;;
uressurizer Water LT459 Foxboro
- 1. UCAP-8341 14 days Yes i.evel Signal LT460 Model E13-DH
- 2. Uectiny, house mininus Transmitter LT461 letter flied on D. C. Cook docket
- Stcan Generator LT517 LT537 Barton Franklin Institute
> 1 minute Indeterninate l'ater Level Signal LT518 LT538 Model 384 Research Lab Report Eransmitter LT519 LT539 C-2623 LT527 LT547 LT528 LT548 LT529 LT549 5 Uide Range PT403 Ba rton None Not tested Induterminate Jre:suie Signal PT405 Model 389 Zransmitters n., Tcold TE413 A & B Rosero at WCAP-9157 14 days Yas i:ui Thot T:423 A & B Model 17eKS TL433 A & B TE443 A & B This reference not included in attachment No. 3 of 6/12/79 submittal, as this letter has not yet been made available to PCE from Westinghouse.
A LTI 43 l;'
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Pcdand General E!ectric Con pany Jrne 15, 1979 Page Five PCE Response Representative Class IE equipnent located in the Containment that must function as described in Tables 3.11-1 and 6.2-1 of the FSAR was selected for the environnental qualification survey. The circuits for this equipment were checked from the Containment penetration to the end device to insure t h a t. all components such as connectors, terminal blocks, and splices were in accordance with the design drawings.
Color narked prints, showing the cable routing, were developed for the survey teaa to aid them in following the cables in the plant.
The survey teaa developed a checkoff list for each circuit that identified the circuit and all i ts components between the Containaent penetration r.J the end device. The checkoff list infornation was then cocpared with the design drawings to identify any " unqualified" Co7ponenrS.
The survey was completed by Decenber 19, 1978.
4 Confir: radiation qualirication exposure for Class lE items in the Control and Auxiliary Buildini;s.
PGE Pesponse_
Radiation qualification noted on Attachment 3.
5.
Confirn that environmental testing was sequential and the effects cunulative.
PGE hesponse Refer to the "Renarks" coluan for equipment in Attachment 3.
Based on the above, we have concluded that proper documentation exists to assure that the safety-related electrical equipment will function under the environmental conditions created by the postulated loss-of coolant accident and r:ain stream line break, as specified in the Trojan Final Safety Analysis Report.
Supplemental information will be provided to address in-Containment signal transmitter qualifications and interim backup conitoring.
541 160
e TROJA.M N'nEAR PLANT Tage 3 ENV!FO'WAL Qi'ALIFICATIN7 FT 'IEk' CF CLAM 1E FL?C*Rf CAL FC"!PPENT ATTAC"'ONT No. 3 IN5ftr CONTAI WENT June 15, 1977 Vr.NDO't DCCtY.NTATICM
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