ML20138C013

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Informs of Replacement of 53 Tobar Model 32 Series 2 Transmitters Qualified for Mild Environ Conditions,W/ Rosemount Model 1153B Transmitters,Qualified for Harsh Environs Based on Vendor 860227 Part 21 Rept
ML20138C013
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 03/26/1986
From: Corbin McNeil
Public Service Enterprise Group
To: Adensam E
Office of Nuclear Reactor Regulation
References
REF-PT21-86 NUDOCS 8604020061
Download: ML20138C013 (10)


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Pubhc Service Electric and Gas Company Ctrbin A. McNeill, Jr. Public Service Electnc and Gas Company P.O. Box 236,Hancocks Bridge, NJ 08038 609 339-4800 vice President -

Nuclear

March 26, 1986 r

8 Director of Nuclear Reactor Regulation

-United States Nuclear Regulatory Commission i

7920 Norfolk Avenue Bethesda, Maryland 20814 Attention: Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing

Dear Ms. Adensam:

EQUIPMENT QUALIFICATION REGARDING ELECTRONIC TRANSMITTERS
HOPE CREEK GENERATING STATION i DOCKET NO. 50-354 1

l Subsequent.to our letter dated February 25, 1986 (C.A.

- McNeill, PSE&G to E. Adensam, NRC), fifty-three (53) Tobar Model 32 Series 2 transmitters included in the harsh Environ-mental Qualification Program were found to be supplied with polyester housing and base assemblies which were not 2

qualified to the requirements imposed by the procurement specific"4 in and committed to in the HCGS FSAR. This

! was verbally reported to NRC by Tobar, Inc. on February 27, 1986 as a possible 10CFR21 reportable incident. This was then followed by a written report to the NRC as a 10CFR21

reportable incident by Tobar, Inc. in letter dated March l 3, 1986 (T.R. Fisher, Tobar, to Director OI&E, NRC).

{ A program was immediately initiated to qualify the polyester housing and base assemblies to the imposed environmental requirements. During this test program, the electrical

, amplifier assembly of the transmitters failed to function during irradiation testing. This was verbally reported

to NRC by Tobar, Inc. on-March 14, 1986.

As a result, the fifty-three Tobar Model 32 Series 2 transmitters which, although could not be qualified for harsh environmental conditions, are qualified for mild environments, will be replaced with Rosemount Model 1153B transmitters which are qualified for harsh environmental conditions. The qualification of these Tobar and Rosemount transmitters is documented in the HCGS Environmental Qualification Summary

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Director of Nuclear 2 3-26-86 Reactor Regulation Seven (7) of the Tobar~ transmitters will be replaced with Rosemount 1153B transmitters prior to fuel load. These seven transmitters are components within the Safety Auxiliaries Cooling System (SACS) and the Residual Heat Removal System (RHR). Six transmitters in the SACS are being replaced to support normal operation of this system which will be required at fuel load, and the seventh transmitter, in the RHR system, was originally planned to be replaced at the time the test plan was developed for the polyester housing / base assembly qualification. The balance, or forty-six (46) of the polyester style Tobar transmitters, will be replaced with Rosemount ll53B transmitters prior to initial criticality.

All fifty-three transmitters being replaced are located in areas outside primary containment, but inside the reactor building. The environmental conditions in these areas are not capable of becoming harsh until after initial criticality is achieved. Therefore, these transmitters will only experience mild environments prior to initial criticality.

The attached FSAR changes reflect the replacement of the Tobar transmitters and provide information that the areas in which these transmitters are located will only experience mild environments prior to initial criticality. These changes will be included in Amendment 15 to the HCGS FSAR.

Revisions will be made to the HCGS Environmental Qualification Summary Report (Rev. 4) to include the transmitter replacements.

These revisions will be included in an addendum which will be submitted with our responses to NRC-EQ Branch questions regarding our letter of February 25, 1986.

Sincerely,

Director of Nuclear 3 3-26-86 Reactor Regulation Attachment C D.H. Wagner USNRC Licensing Project Manager R.W. Borchardt USNRC Senior Resident Inspector H. Garg USNRC EQ Branch

r' ATTACHMENT

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HCGS FSAR 09/85 Radiation exposures to components will be minor and will-be due to two sources: radiation shine, and immersion in airborne radioactivity released in a controlled manner from the reactor building.

The TID from both sources will be less than 100 rads for 180 days.

3.11.1.3 Excluded Systems'- NSSS and Non-NSSS Table 3.11-8 shows the systems designated as seismic Category I in Table 3.2-1 that are to be excluded from the HCGS Environmental Qualification Program.

The table identifies each system with correlation to Table 3.2-1 and the reason for exclusion from the HCGS Environmental Qualification Program. ~

3.11.1.4 Environmental Conditions - NSSS and Non-NSSS The environmental conditions shown in Table 3.11-1, and the associated figures may be changed at a later date because of continuing evaluations that are being performed on a case by case 4 basis, s, luSERr--*

3.11.2 QUALIFICATION TESTS AND ANALYSES 3.11.2.1 NSSS Safety-Related Class 1E Electrical Equipment Harsh Environment Oualification Components of the nuclear steam supply system (NSSS) Class 1E electrical equipment are qualified in accordance with the environmental qualification criteria and guidelines specified as Category II in NUREG-0588, " Interim Staff Position on -

Environmental Qualification of Safety-Related Electrical Equipment," dated December 1979 (for comment), and IEEE-323-1971, "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations." However, the HCGS environmental ,

qualification program has upgraded qualification of equipment to '

l the requirements of NUREG-0588, Category I and IEEE 323-1974.

Components of the NSSS Class IE electrical equipment in a harsh i environment are qualified by test, or a combination of testing and analysis. Those components used in more than one system, which can be or are located in different plant areas, are

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INSERT TO FSAR SECTION 3.11.1.4 The environmental conditions that components may be exposed to in areas outside primary containment, but inside the reactor building, are.not capable of becoming harsh until after initial criticality'is achieved.

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. 1/P6 i MCG5 FSAR Page lo of 189 TARLit 3.15-5 EOUIPMENT SELFCTFD FOR HARSH FNVIRONMENT OUALIFICATION P&lp M-Il-l

  • SYSTFMe SAFETY AUR COOL SYSTEM EG PAN TNI ACTION in No. LOCATION EOUIP. Pl.AN Fotfl P .

P.O. Note (5) NPL NO. COMPONFNT BLDG, FI.FV. NOTE (1) NOTF (25 FFSR RFF. No, et00 4 1 -rG- Plyr-2 4 8 5 A Diff. Proes Trane, peactor 102 No No in iWA M005 3-FG-PDT-2485R Diff. Press Trane, peector 102 No No 155 ICA Mnot 1-FG-PDT-2405C Diff. Prees Trans. Reactor 102 No No 155 , itJJA Munt I-FG-PDT-24p50 Dilt. Press Trans. Reactor 102 No No 155 J2040 l-FC HS-2405A2 Nano Switch pesctor 102 No No 25 J20lO l-EG-MS-2485p2 Nand Switch peactor 101 No No 25 52010 l-EG=HS-2485C2 Hand Switch peector 102 No No 25 JJolO I-EG-NS-2485D2 Hand Switch peactor 102 No No 25 P1050 1-FG-HV-249IA Contr. Velve peactor 102 No No 144 P1050 3-FG-IS-249BA Limit Sultch peactor 102 No No les P3050 1-FG-HV-249tn contr. Velve peactor 102 No No 144 PIU50 l*EG-IS-14918 Limit Switch peactor 102 No No 144 P1050 1-FG-HV-24944 Contr. Valve peactor 102 No No 144 P1050 1-FC-IS-24944 Limit Switch peactor 102 No No 144 P3050 I EG-HV-24948 Contr. Valve peactor 104 No No 144 P)D50 1-FG-IS-2494R l.imit Switch .peactor 102 No No 144 PID50 1-FG=HV-2496A Contr. Valve peactor 102 ko No lee Ptn%Q 3-FG-tp-24944 1.imit Switch paattor 102 No Na s $44 ricio 8-rc-HV-2496R Contr. valve peactor 102 No No 144 P1050 1-FG-SS-24968 Limit Switch peactor 102 No No 144 P1050 l=EG-HV-2496C Contr. Valve peeCtor 102 No No 144 P9050 1-FG-ts-249&C Limit Switch peactor 102 No No 144 P1050 3-FG-HV-24960 Contr. Velve pesctor 102 No No 144 P3050 4-FG-IS-2496D Limit Switch peactor 102 No No 144 J1010 1-FG-LT-2500A l.evel Trane. Reactor 204 No No ISEA J3010 1-EG-LT-2Suun Level Trans. Reactor 208 No No IS J30lO I-EG-LT-2500C Level Trene. peactor 201 No No 29

, J10lO l-FG-LT-25000 Level Trane, peactor 208 No No 29

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NCCS FSAR 1/06 Page 12 of 119 TARLE 3.11-5 EOulPMENT SELECTED FOR NApSH FNVIRONMENT OUALIFICATION P6fD sysTrMs SAFETY AUX COOL SYSTEM M-!!=l FG PAM TMt ACTION ID NO. LOCATION FOUIP.

P.O. PLAN EOulP.

Note 155 MPL NO. COMPONENT RLDC. ELEV. NOTE (3) NOTE (2) EESS BEF. NO.

P1050 1-EG-HV-2522C Control Velve peactor 102 No No 147 P30%Q I-rG-IS-2522C Limit Switch peactor 102 ko No 147 P1050 4=EG-HV-2522D Control Valve peactor 102 No No 147 P3050 l-EG-25-25220 Limit Switch peactor 102 No No 147 J20lO l-rG-MS-25220) Nand Switch peactor 102 No No 25 J10lO l-tC-PDT-25294 Press. Diff. Trane, peactor 162 No No 29 J1010 l-EG-Pirr-2 5 298 Press. Dif f. Trane. Reactor 162 No No 29 J%%40 1-rG-TE-2535A Temp. Element peactor 102 Yes No 4)

.35560 4-EG-TE-25358 Temp. Element peactor 102 Yes No 41 J10lO l-FG-FT-2544A Flow Trane. Reactor 102 No J10lO l-FG-FT-2544R Flow Trane. Reactor 102 No No E' lgg No Is5A J)DIO l-ZG-FT-2544C Flow Trane. Reactor 102 No No Af*-& gg g J10lO l-EG-rT-25440 Flow Trans. Reactor 102 No J10lO l-FG-FT-2549Al Flow Trane.

No g gg g Reactor 102 Yes No 29 Jinto I-rC-FT-254983 Flow Trane. Peactor 102 Yes No .29 JJnIO I-rC-FT-J54993 Flow Trane. Reactor I t'2 No No 29 r10%O 1-EG-HV-7928A Contr. Valve peactor 162 No No 144 r3n50 3-EG-IS-7921A Limit Switch peactor 162 No No 144

, P1050 1-EG-HV-79219 Contr. Valve peactor 162 No No 144 P1050 1-EG-IS-792in Limit Switch peactor 162 No No 144 P3050 1-EG-HV-79224 Contr. Valve peactor 162 No No 144 P3050 1-EG-25-7922A Limit Switch peactor 162 No No 144 P3050 1-EG-HV-79228 Contr. Valve peactor 162 No No 144 P3050 1-EG-IS-7922R Linnt Switch peactor 162 No No 144 Amendment 14

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TARI E 3.11-5 FOtllPMENT SFLFCTFD FOR NApSN FNVIRONMENT OffALIFICATIDN P&fD NYMTEMe DFSIt)UAL NFAT DFMf7 VAL SYSTEM DC PAN TMI ACTION ID HO. LOCATION EOUIP. PLAN rots t P .

P.O. NOTE ISS MPL NO. COstPONENT RLDC. ELEV. ISOTE (1) NOTF (23 FFSS PFF. NO.

s anol I-nC- PT-M 0 5 6 N Ell Press. Trane peactor 54 No ' No 155

. muol 3.nc-PT-N057 Eli Press. Trans. Reactor 77 No No 106 8H"J I l-DC-PT-NO5SA Eli Press. Diff. Trans. Reactor 77 No No ISS

=005 l-MC-PT-N05AM Ell Press. Diff. Trane. Reactor 77 No No 155,15EA mool I-pC-PT-N058C Ell Pr e s s . Diff. Trang. Peactor 77 No No 155 anot 3-DC-PT-N0590 Eli Press. Diff. Trans. Reactor 77 No No 155,333k N001 3.nc-PDT-N0 6 0 A Eli Press. Diff. Trane, peector 77 No No 106 anol 3-pC-PDT-N060M Ell Press. Diff. Trans. Reactor 77 No No 106 D64159 l-nc-TE-N027A Temp. Elemt. Reactor 77 Yes No 14 FAMI59 l-RC-TE-M027n Temp. Eleet. Reactor 77 Yes No 14

.35560 l-PC-TE-4401 Temp. Elemt. Reactor 77 No P'r 3 4)

.33080 l-RC-FT-4435 Flow Trane, peactor 77 No do 29 Pluto I-nC-NV-4419 Control Valve peactor 77 No No 127 P10lO l-RC-25-4439 Limit Switch peactor 77 No No 127 JBolO I*RC-FT-4461A Flow Trane, peactor 77 Yes No 29

.39n10 1-nc-FT-4468R Finw Trano, peactor 77 Yes No 29

. Into I-RC-FT-4462A Flow Trane. Reactor 102 Yee No ISSA

.I1410 1-DC-FT-44628 Plow Trane, peactor 77 Yes No Amendment le a

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1/nr, necs rsAs TARLE 3.II-5 ,,,,, ,,,,,, it, NOTFS'

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.. and vs ide.nt l f le.e s so- iethe equipm,e,nt.

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ineat ed i n w harsh envi ron= ant required for poet accident monitoring ag anginca in 128 Thle entumn identifies the equipment located in a horah environment identified og tMI Action Plan Rqulpmentag defined in

( Il Iteme that are generle are purchemed and used throughout the plant'and may be used in the DRA Harsh Environmant ,

lel Eteetric renetration Asee.blies for ecstral and instruaentation circulte include inline splice connnector hise.

til f.lat t or pne tt len owltch tag numbers have been created by velng the *IS* designator in lieu of the salve SHV8 elaelgnetor och*=et les or fort he purposes Spetrument of equipment inden. quellfleetion accountability only. These tag numbers may not be f ound in rssn'e, un,ter m001 lN3SSI P.O. Faceptione to thle occur when poeltlen switchee are mounted on manuel valves or are

% In that case the tag numbers pey be found in the instrument Indes and appfleable P&lD's.

169 Transmittere Electronic Circuit with EESSBoarde Ref.prior No. to29 initial will becriticality, changed to Rosemount !!53e Transmittore utilising output*R*code s

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