ML19249B281
| ML19249B281 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/17/1979 |
| From: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| NUDOCS 7909040230 | |
| Download: ML19249B281 (6) | |
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July 17, 1979 Trojan f;uclear Plant Docket 50-344 License I;PF-1
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Mr. R.
II. En!;e lke n, Director U. S. I;uclear Regulatory Connission
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Region V S,
a Suite 202, Walnut Creek Plaza 8' "
q 1990 I;. Californla Blvd.
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Ualnut Creek, CA 94596
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Dear Sir:
j Attached please find the supplement al inforr'a tion as indicated in ny letter to you dated May 18, 1979, which subnittect our response to Iten 13 of IE Eulletin 79-06A, Revision 1.
The attached table sun-narizes the description and inplementation schedule of design nodifi-cations at the Trojan I!uclear Plant as a result of the prelininary review of the T'!I accident.
The inplementation schedule described in the table represents our best estiration t> date based on available naterial delivery dates and the Trojan plant operational schedule.
A review of the Administrative Section of the Trojan Technical Speci-fications is currently undetvay.
Sone possible organizational changes have been' identified and are bein;; further reviewed and evaluated. This additional review and evaluation should be cenpleted within 60 days.
Should some of these organizational changes be desirable or necessary, a request for a license amendnent will be submitted within 30 days after completion of the review or by mid-October 1979.
Our survey and evaluation of nanagement end technical resources in response to Harold Denton's letter of June 29, 1979 will supplenent our current review and will be submitted to you by July 30, 1979.
In addition, a sufficiently high priority has been given for reviewing the Radiological Energency Response Plan (RF.RP) in light of the TMI 7909040 2 2 O
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1:. Engell.en July 17, 1979 Page 2 cur rently workin ; with the State of Orer,on on the accident. We are Oregon Energ,ency Operations Plan which will be sutwitted to the I:RC fo r concurrence this fall. We alco hope to have amended the Trojan RERP by this fall to incorporate those TIll-related changes presently identified.
Sincerely,
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C. Goodwin, Jr.
Assistant Vice President Thernal Plant Operation and fla int ena nce CG/R!/4sb8A16 Attachnent c:
IIr. Lynn Frank, Director State of Oregoa De pa r te.e p t of Enerr,y a,,;na.,.
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.,. nc Page 1 of 4 IMPLEMENTATION SCHEDULE OF DESICN MODIFICATIONS IDENTIFIED AS A RESULT OF PRELIMINARY REVIE'.J OF TlIE TMI ACCIDENT Status of Desir,n Implementation Trojan Design Echedula Modification Description of Design Modification Review 1.
SI Initiation Disconnect the input relays of the Completed.
Modifications were Logic Change pressurizer level bistables at the implemented and the universal logic boards in the SSPS system is currently in cabinet and change the input relay service.
connectors of the pressurizer pres-sure bistables to produce an actua-tion signal from a two-out-of-three logic.
2.
Containment Change the control circuits of Con-Preliminary design Modification will be Sump Discharge tainment isolation valves M0-4180 review stage.
Implemented before the operation (l)ycle 3 startup of C and CV-4181 on the Containment sump line (FSAR Figure 11.2-14).
This is to climinate, following a Containment isolation signal reset, the automatic pumping of waste water out of Contain-ment if a high Containment sump level exists.
In addition, a process radia-tion monitor will be installed on the Containment sump discharge line to monitor activity level of the liquid to be transferred from the Containment sump to the Auxiliary Building dirty
,g waste drain tank or the clean waste g
receiving tank.
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Page 2 of 4 IMPLEMENTATION SCIIEDULE OF DESIGN I:0DIFICATIONS IDENT] PIED AS A RESULT OF PRELIMINARY REVIEW OF Tile T'II ACCIDENT Trojan Design Status of Desi;;n Implementation Schedule Modification Description of Design Modification Review 3
PERM Range Increase the upper ranges of the Detailed design Modification will be Auxiliary Euilding and main condenser review stage.
implemented before the operation (l)ycle 3 startup of C air ejector Process Effluent Radiation Monitors (PERM-2 and PERM-6, respec-tively).
The upper range of PER'!-2 and PERM-6 will become 3 x 102 pCi/cc (Xe-133).
4.
Redesign of Modify the control circuits of Con-Prelimiary desi;;n Modification will be Centainment tainment isolation valves which auto-review stage.
inplemented before the Isolation matically open, if previously in an startup of Cycle 3 Valve Response open position, after the Containment operation (l).
on Resetting isolation signal is reset.
Approxi-Containment mately 21 valves will be modified to Isolation prevent automatic opening after Con-tainment isolation signal reset.
With present Trojan design, one of the redundant serics Containment isolation valves in each line remains closed until opened by separate operator action, except steam generator blow-down sample line valves.
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Page 3 of 4 IMPLEMENTATION SCl!EDULE OF DESIGN MODIFICATIONS IDENTIFIED AS A RESULT OF PRELIMINAFY REVIE',i CF TIIE TMI ACCIDENI' Trojan Design Status of Design Inplementation Modification Description of Design Modification Revicu Schedule 5.
Recycle Provide a cross connect return line Preliminary design Modification will be Connection from the waste gas decay tanks to the review stage.
implemented before the From Waste Containment Building. Waste gas will startup of Cyc le Cas Systen be discharged back to Containment operation (2),
to Contain ent from any waste gas decay tank or pumped back directly from the waste gas compressors by manual alignment of the valve and spool piece which will be located on the return line.
6.
Low Suction Install a low suction pressure trip Preliminary design Modification will be Pressure Pro-switch for each auxiliary feedwater review stage.
icplemented before the tection for pump,or an equivalent protective startup of Cycle 3 Auxiliary device.
operation (l).
Feedwater System (AFS)
Punps 7.
Electric Add an electric totor-driven AFS Detailed design Modification will be Motoi-Driven pump which is capable of delivering review stage.
implemented before the AFS Pump 1000 gpa at a head of 3400 ft.
The Piping is startup of C operation (l)ycle 3 new pump will take suc tion from the installed.
condensate storage tank and provide flow to an existing AFS pump discharge line.
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Page 4 of 4 IMPLEMENTATION SC11EDULE OF DESIGN MODIFICATIONS IDENTIFIED AS A RESULT OF PRELIMINARY REVIEW OF TiiE T !I ACCIDEN C Trojan Design Status of Design Implementation Modification Description of Design Modification Review Schedule 8.
Status Install position indicators to the Preliminary design Modification will be Indication AFS manual valves that isolate the review stage, implemented before the of AFS Manual totor-operated control valves.
Indi-startup of Cycle 3 Valves cation of these valve positions will operation (l).
be located at panel C05 in the con-trol room and locally at panel C160 in the form of red and green indica-ting lights.
9.
Independent Add a self-cooling uater supply to Detailed design Modification will be Cooling Water the AFS pump lube oil and bearing review stage.
implemented before the operation (l)ycle 3 startup of C Supply for heat exchangers to ensure that pump Turbine-Driven operation will be independent of the AFS Punp Service Gater System.
The self-cooling water will be taken from the AFS pump discharge.
(1) Cycle 3 operation is currently expected to commence in the first half of 1980 (February thru May).
(2) Cycle 4 operation is expected to commence in the spring of 1981.
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