ML20136C067

Site Problem Rept 113 Re Reactor Protection Sys Inputs. Startup Problem Rept 2089 & Response Encl

ML20136C067
Person / Time
Site:	Three Mile Island
Issue date:	02/28/1977
From:	Jonathan Brown, Pletke L, Rogers L BABCOCK & WILCOX CO.
To:
References
TASK-TF, TASK-TMR 113, PROB-770228, NUDOCS 7909140350
Download: ML20136C067 (4)

Text

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o s m nmuxu o REPORT TRANS!11TTAL

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FILE: 13- lo - II3 TO: CS4 aj e [*v b o[ For Distribution CONTRACT NO: 620-00 O (o .

S. JI. Klein - Qualfty Acr,uranc SPR lI3 Central Engineering Files TII'LE RP.S. .ruds '

A E. Ma molo- Task Ennincer L. R. PloGe- pron.ct nananct

, DATE: '3-4-77 C

STATUS CODE E. L. Logan - FLORIDA L. C. Rogers - MET. ED.

F. R. Faist - TOLEDO B. L. Day - Intl. Support J. L. Donnell - 0FR B. A. Karrasch - Plant Integration Attached is one copy of Site Problem Report No. //3 _ vhich was processed on Contract 620-00 6 6 . Futurc ' contracts have been reviewed for the potentJal of a similar prob 1cm. Thin problem Jo/is v.ct conuddered applicahic to other cohtracts .

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• J PROBLEM REPORT 2089

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1. TMI-II Tech Specs. - Chap.16, Sect. 2.3 details cafety analysis calculations vs. Reactor Protection System setpoints as specified in Chap. 16, Tabic 2.3-1. Picase confirm that the setpoints as listed in the above referenced table may be inserted into the RPS system without further consideration of instrument accuracy and ,

calibration errors - provided that:

a. Calibration procedures and equipment per B6W/ Bailey Tech Manual- l l

Instruction Book f or Nuc1 car Instrumentation and Reactor l Protection System - Vol. 2 0029-00 are used.

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b. Head corrections per your response to Problen Report 2087 are accounted for. .

2. What allowances were made, if any, for instrument and calibration l errors in the selection of the 4 psig setpoint for Reactor Building pressure. B&W did not supply the sensors for this signal on TMI-2.

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1. The RPG trip setpoints precented in Chapter 16 of the FCAR vere developed based on accumed values of key fuel parametera and the analysis techniques in use at that ti:ae. The tech cpee format and the philocophy of error treatuent has been altered by the NBC-iucued 16W standard tech specc. In both cases (Chapter 16 and 1EW ctandards), all errorc, unobservable and observable inaccuraciec , non-linearities, calibration bando, and drif t are included in determining the trip cetpolats. However, the chanceo identified above (as-built vercus accuned fuel parwncterc, error analycic changec, and trip cetpoint analyclo techniquea chanceu) nahe the Chapter 16 cetpoints not applicable for une in the HPS. It is recommended that GPU valt for the B&W cafety analysis input for use in the TMI-2 Tech Spec. This input vill be incued in by 1977 and vill be in the B&W l standard tech cpec format.

2. The reactor building prescure cuitch is accumed to actuate at 4 psic and no allowance for errors, drif t, calibration, accurney, etc. , are included.

GPU chould determine thoa2 allavances that must be accounted for to accure that the actual trip would not occur at a preccure in exeecs of h.0 psic.

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