ML19345G216
| ML19345G216 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/30/1981 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-01B, L1L-026, NUDOCS 8103170111 | |
| Download: ML19345G216 (6) | |
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.A Metropolitan Edison Company gh' Post Office Box 480 Middletown, Pennsylvania 17051 717 944-4041 Wnter's Direct Dial Number January 30, 1981 L1L 026 Office of Inspection and Enforcement D
Attn: B. H. Grier, Director p\\
Region I g
U. S. Nuclear Regulatory Commission f
]
i hu.l,f/!,[?yOI981. s 631 Park Avenue King of Prussia, Pa.
19406 O
$$4ratr
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1) h Operating License No. DPR-50 Docket No. 50-289 Response to IE Bulletin 79-01B In accordance with Item 1.b of Supplement No. 3 to IE Bulletin 79-01B, we are hereby forwarding a master list of equipment and qualification sheets for one qualified path to achieve cold shutdown.
Supplement No. 3, Item 2a, also required submittal of qualification information by February 1, 1981 for lessons learned equipment in harsh environments needed to mitigate the consequences of LOCA's or HELB if the equipment is installed.
At this time, only portions of these systems in harsh areas are completely installed.
Therefore, as specified in Item 2, the environmental qualification data vill be provided with the preimplementation review data, if required (Item 2b), as soon as possible for equipment under NRC review (Item 2c), or by the implementation date, if no creimplementation review is required (Item 2d).
The qualification data for one identified path to cold shutdown is provided complete, except where vendor data has not been received, or where lessons learned equipment is used (RCS high point vents).
The licensee is continuing to evaluate additional paths and updates as necessary will be provided.
Since our October 31, 1980 submittal (TLL-560), we have received additional information to resolve many of the open items on the hot shutdown qualifica-tion sheets.
In addition, the material evaluation sheets have been reformatted and upgraded.
The additional information and revised format only affect a small portion of the data previously submitted; however, many pages are affected.
In order to avoid confusion for updating volumes, we are providing complete replacement volumes for hot shutdown (Volumes I and IA).
The revisions made to the previously submitted information are summarized in.
,Si cerely, f
ki 1 Director, TMI-1 HDH/CWS:jes Enclosure 8103170///
cc: R. W. Reid - w/o Encl.
D. DiIanni - w/o Encl.
Metropol. tan Ed: son Company is a Member of the General Pubbc Utihties System
METROPOLITAN EDISON COMPAhT JERSEY CENTRAL POWER & LIGHT COMPAhT AND PENNSYLVANIA ELECTRIC COMPAhY THREE MILE ISLAND UUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 This letter is submitted in response to the Nuclear Regulatory Commission request concerning IE Bulletin 79-OlB, " Environmental Qualification of Class lE Equipment,"
dated January 14, 1980 for Three Mile Island Nuclear Station, Unit 1.
All state-ments contained in this report flave been reviewed, and all such statements made and matters set forth therein are true and correct to the best of my knowledge, information and belief.
METROPOLITAN EDISON COMPAST By i
M Dife :Cor, TMI-l Sworn and subscribed to me this 1 day of O M4taxx4
, 1981.
/
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7 By O
Notary ub 4,c' PAMELA 10Y LUE:Ca,!K; Nxry Pdne
- Eddetown, c::;his C:uty, P.s My Correissi:n Expirss Aagust 21 G33
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FtCLOSURE 1 i
Item Page Description Revision MAIN STEAM SYSTD4 PS-600-1-8 SLR Pressure Resolved open items arni new PS 607 Switch new materials evaluation SP6A-Pf-1&2 9-12 CfrSG Pressure Updated open items for ongoing SP6B-PT-1&2 Transmitter evaluation LEA /MS-V-6 13-14 Limit Switch Identified switch as not being LSB/MS-V-6 replaced LEA /MS-V-13A&B 15,16,19 Limit Switch New material e; valuation LSB/MS-V-13A&B 20 Sv/MS-V-13A&B 17-18 Sole 3oid valves Resolved ASC3 status. New material evaluations a
EHETCLNCY FEEDWATER/FEEDWATER SYSTEM All pages have new system name.
FW-V-9 2A&E 11-14 Feedwater Block Updated with recent vendor FW-V-5A&B valves Data SilEF-V-8A&B&C 15-20 EFP Minimum flow Added components to Master FIS-77&78&79 valves & sensor list Sv/FW-V-16 21B 21-27 Feedwater control Added components to Master List Sv/FW-V-17A&B valve Solsnoids MkEE-UP AND PURIFICATION SYSTDi M7-P-2-A&B&C 4-9 Make-up Lube oil Now material evaluation JE}-P-3-A&B&C pump l
l LSa/stJ-V 15,16, limit switch New material evaluation (vazious) 26-29 l
LSE/MI-V (varlaus) 32-53 STAT 0-V 17,25,30 Solenoid valves Resolved ASCO status.
New (various) 34 material evaluations PS-480-A&B&C 37-39 Pressure switch New material evaluations
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D1 CLOSURE 1 (csntinu3d)
Item Page De scription Revision DECAY HEAT REMO7AL - NO CEANGE DECAY HEAT CIOSED IDOP CDOLING SYSTEM SV/DC-V-19AsB 36 Solenoid Valvea Resolvsd ASCO status.
New material evaluations LSA/DC-V-19 4,5,7,8 Limit switch Updated with recent vendo:
Ar.a data IM/DC-V-19 AE7
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REACTOR BUIIDING ISOLATION SYST*M LSA/ various 1,2,7,8, Limit switches New material evaluation LS2/ various 13,14,18, 19,21,22, 25,26,28 29,31,32 34,35,37 38,42,43 46,56,57
$9,60,62, 63,65,66 SV/ various 3,4,9,10, Solenoid valves Resolved ASCO status. New 12,23,27 material evaluation 30,33,36, 3'3,41,44, 49,55,61, 64,67 i
RD-V-7 51-53 REECS norsal cooling Valve replaced with limitorque outlet valve motor operator WDG-V-3se.
54-57 R.B. Vent header Changed specification to ISO. valves reflect cold chur.down applicability l
ENCLOSURE 1 (continu3d)
I 1
Item Page Description Revision REACTOR BUILDING SPAY SYSTDi - NO CHANGE
_ REACTOR PROTECTION SYSTEM E4A-TE2,3 5-8 Temperature New material evaluatien RC45-TE23 Transmitter PS-672s4&5 13-15 Pressure Switches New material evaluat3ans s
, ENGINEERED SAFEGUARDS ACTUATION SYSTEM PT-282s5s8 1,4,7 Pressure Updated open items for ongoing Transmitters evaluation PT-283s4s6 2,3,5,6 Pressure switches New material evaluation PT-237&9 E290 8,9 RC3A-PT3s4 10-12 Pressure Updated open items for ongoing Transmitters evaluation REACTOR BUILDING EMERGENCY CDOLING SYSTEM - NO CHANGE REACXY"R BUIIDING COOLING RIVER WATER SYSTDt - NO CHANGE CORE FLOOD SYGTE_M CF-V-37.EB 3,6 Core Flcod Tank Changed specification to vent valves reflect cold shutdown applicability LSA/CF-V-19&20 11,12 Solenoid valves Resclved ASCO status. New material evaluations t _
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Item Page Description Revision NUCLEAR SERVICES CI4 SED LOOP COOLING SYSTEM CS-V-4&l5 4-7 R.C. Cooler Changed specification to NS-V-32&35 ISO. Valves reflect cold shutdown applicability LSA/NS-V-52 8,9,11, Limit switch New material evaluation 653 12,14,15 LSO/NS-V-52 17,18,20,
&53 21,23,24 SVAIS-V-52&S 3 10,13,16, Soler.oid Valves Resolved ASCO sta'.us.
New 19,22,25 material, evaluation ADDITIONAL ACCIDENT MONITOR EQUIPMENT /3EACTOR COOLANT SYSTEM All pages'have new system name i
SP1A-LT2&4 1-7 Level Transmitters Updated open items for ongoing SP13-LT2&4 evaluations RC5A-TElt2&3&4 8-15 Tamperature New matarial evaluations BCSB-TEl&2&3&4 Transmitter COMMON CVSTEM Terminal Block 2
Terminal Block New Material evaluation.
Updated irradiation lA&lB&lC ES VLVCC 6-8 Va'lve Control Center specifications to non-harsh environment CALCULATIONS 0370-025-028 REV. 1 Effects of DBA's on thermal aging sensitive materials 0370-025-030 REV. O Arrhenius model for neoprene 0370-025-033 REV. O Arrhenius model for ethylena propylone rubber 0370-025-041 REV. O Pressure evaluation of SOR pressure switch
.0370-025-042 REV. O Stress calculation of an SOR pressure switch due to a pressure environment..
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