ML19225D118
| ML19225D118 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/22/1979 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IP-NAP-5146, NUDOCS 7908070362 | |
| Download: ML19225D118 (2) | |
Text
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POWER Al ORITY OF THE STATE OF NEW YORK
~Th IN Ol A N PO? NT NO. 3 NUCt.E AR POW E R Pt. ANT e o ao' als stucw a w aw. % y.sosts
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.fune 22, !? 19 IP-NAP-5146 Docket No.30-286 License No. DPR-64 Boyce H. Grier. Director of fice of Inspecticn and Enforcenent Region 1 U. S. Suelcar Faculat.ory Ce:r:1?sion 631 Park Ave,ne King of Trussia. Tennsylvania 19406
Dear Mr. Grier:
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In accordance with the Technical Specifications of Tacility
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Operating Licenae No. DPR-66, the folles-ing describee Reportable Occurrence (LER) 79-906/01T-0.
This event is the type defined in Technien1 Specif.ication 6.9.1.7 (hb
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On June 21, 1979, the Tower Authority Na 'notifiAd kIour, i
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m Nucl ar Steam Supplier, the Vestinghouse Elcetric Corporation,' of.
an error in the less censervative direction in their analysis efa -
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high energy line breaks inside centainment. " Breaks of this type ran' result in heatue of the stess generator level ressurement reference 1en Teev1t ing in a decreene of the weter column den =ity vith a con-cequent apparent incresee in the indicated steam generator water Icvel
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(i.e.,
apparant level creeedinn actual 3evel).
This potentisl level bias could result in delayed protect.lon Signals (rcactor trip and auxiliary feedwater initiation) which are based on lev-Iov Fream gen-erator water level.
In the esse of a feedline rupture, this adcerse.
-environeent could be present end could delay or prevent 'the primary.
signal art eing from declining stna : p rmtor varer level (Iow-low
-s t een eenera tor "l evel).
Containment pressure and safety injection provides a backup sicnal which initinto e trip before a contai-iment te perature of 200" T.
is reached.
This trip in enn=ervatively set at 1.0 psit.
Vestinghouse has calculated that raising the steam separator
.ow-lov leval setpoint bv 10 per cent. of spen would ennpennete fnr the
- -f fects of this re :perature.
Since the power Authority's calibration procedures alrendy use a velve of 15 per cent of span an opposed to the Technten! Specificatien value of 5 per cent, and containnent pressure trip of 3. psig es opposed to Technical Specification value of 3.5 psig,
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rhe change in setpoint reco= ended by vestinghouse is already in effect.
Further evaluation will he conducted td deterciine final setecint adjustments.
EM o 08030 A27 117 s,s
Boyce H. Grier, Directer Pa ge Two J'm a 22, 1979 IP-NAP-51 t.6 For other high ene rgy line bnek.c which could intreduce a siSilar positive bis 9 to t he stem generator watar leW3 treasure-ent, steam Renerator level doe = not provide the prinarv trip f tmetion and the potential bias veuld net interfare with needed protective sy9 tem actuation.
The effects of the temperature increase on ot$er level in[trumntation in containo-nt for post accident nonitoring is being reviewed' n id appropriate
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guidance vill be given t.o the operators.
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The Site Resident inspector, Walter Baunsch, was verhelly noti.fied
. on this date by Salvatore Zulla. This cotstitutes the twenty-four (24)'
-hour formal nerification as required by Technical Specifications..
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Director-of Nurleer Fenetor Reguistion (2 copies')
- Office of Manage:ont Infor serion 6 Progrn*n Control' Z
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U. S. Nuclear Peptistery Comis= ion
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