ML19308C826
| ML19308C826 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/25/1978 |
| From: | Herbein J Metropolitan Edison Co |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19308C823 | List: |
| References | |
| TASK-TF, TASK-TMR GQL-0131, GQL-131, NUDOCS 8002070576 | |
| Download: ML19308C826 (4) | |
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/ METROPOLITAN EDISON COMPANY
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. 1 POST OFFICE BOX 542 READING. PENNSYLVANI A 19603 TELEPHONE 215 - 929 3601 gJaduary.25,1978 G0 f 0131' 7^"
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Director of Nuclear Reactor Regulation f
1 Attn:
Mr. S. A. Varga, Chief k Ub ) I light Water Reactors Branch No. k
, Afl251978* Q-
$7 U. S. Nuclear Regulatory Cor::21ssion Washington, D. C.
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Dear Sir:
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Three Mile Island Nuclear Station Unit 2 (TMI-21 License No. CPPR-66 Docket No. 50-320 Items Which Will not Be Completed Prior to Date Requested For Operating License Issuance We estimate that completion of construction of TMI-2 vill be between January 26 and February 1, 1978. At that time, we anticipate all construction items re-quired for fuel load to be complete. There vill, however, be a number of test procedures, administrative, and QA items that vill not be complete. Attachment 1 is a list of each of these ite=s.
If there are any additions to the list, they vill be provided by letter prier to fuel loading.
' ery truly yours, J. G. Herbein Vice President-Generation JGE:JES:ejg :
" Test Procedure Status at Fuel Load" h0 copies cc:
Mr. 3. E. Grier, Director U. S. Nuclear Regulatory Commis./Aon Office of Inspection & Enforcement Regien 1 631 Park Avenue King of Prussia, Penna. 19h06 3,//
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-m A'.!ACH'C;T 1 Test ?recedure Status at Fuel Lecd CCMPLETION SYSTDI E
STATUS NODE #)
' Hydrogen Peco=biner 160/1 Test incocplete 2
'60/3 Partial Approval-pu=ps do Reactor Building E=crgency 1
Cooling not supply rated flow 4
Reactor Su11 ding Hydrogen 160/4 Flev ele =ent on air dis-A Control charge is inoperable 2
Reactor Building Purge 160/6 Systen operable, valve response ti=a complete, testing incomplete 2
Control Building Area H 171/2 Procedure cocplete but and V results not approved 4
Control Building H&V 172/2 All complete except for toilet fan 4
Auxiliary Building H&V 173/2 Test Procedure incocplete 2
Fuel Handling Building 177/2 Test Procedure ince:plete 2
H&V Surveilance Speci=en 200/2 Test incomplete 5
Handling Decay Heat 203/4 Partial approved procedure with low flow reasurecent incocplete using boron flow sensor 2
Nuclear Plant Sa=pling 210/12 Procedure cocplete; results not approved 5
Secondary Plant Sz:pling 211/1 Procedure inco:plete 1
Waste Evaporator 230/3 Procedure inco=plete - handle vaste in Unic #1 or truck off site 5/1/7G Waste Gas 231/3 Procedure ince=ple:e 2
Solid Waste 232/1 Precedure inco=pic:a 2
l nuclecr' Scrrice Clocad 257/4 Precedure par ici c; pre cd-C:olin; Water
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puno cooling 4
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Main Seca=
271/4
?::cedure inco plete 3
Feedvater Pu=ps 272/1 Procedure ince:plete 3
Emergency Feedvater Pu=ps 273/3 Procedure ince:plete 3
Condensate 276/3 Procedure inco=plete 2
Makeup De=inerali:crs 278/3 Testing not co=plete -
can obtain water frc=
Unit #1 or truck Pretreat=ent 278/4 Testing not co=plete -
can obtain water from Unit #1 or truck 4
Nuclear Instru=entation 301/2 Test Procedure will be Cables co=plete for Source Range.
Inco=plete inter =ediate range and power range.
2
. Nuclear Instru=entation 301/3D 2
Incore Cable Checks 302/2A Procedure inco=plete 2
Reactor Protection 315/1 Procedure co=plete except for FW latching response etze 3
Co=puter Software 350/2 Procedure ince=;lete Verify progress during power escalation Computer Inputs 350/10 Input Verification Radiation Monitors 360/lA, Procedure Partial Approved Will co=plete 3,C monitors to support each applicable =cde Loose Parts Monitoring-365/1
?rocedure ince=plete 5
Heat Tracing 370/1 Procedure inco=plete 5
' Loss of Power 600/20 Procedure co=pleto - not approved 2
Hot Function:1 Sequence
-600/23 Sequence covers :: the end
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of fu el 1 ad a- - ~ ' ' -'-'
TP 710/2 beco=es th2 sequenca 5
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TP Eat Functional E:nger 500/29 Test cceplete - will Testing repeat due to ncjor work inside the recccer com-2 ponents Filter Testing SP 2 Co=plete for Control Building H & V, Reactor Building, Purge & Eydrogen Control 2
Voltage Testing Procedure not written 2
1.
The Site Evacuation Plan will have recent NRC co=ents incorporated, but the FSAR will not be revised to reflect the latest Plan revision.
Will complete FSAR Revision b7 co=ercial operation.
2.
Cannot satisfy ANSI Standard 45.2.9 for caintaining Operating Records.
Will satisfy by June 1,1979.
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