05000272/LER-1983-013, Forwards LER 83-013/99T-0.Detailed Event Analysis Encl

Forwards LER 83-013/99T-0.Detailed Event Analysis Encl

ML20071D803
Person / Time
Site:	Salem
Issue date:	03/02/1983
From:	Midura H Public Service Enterprise Group
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20071D810	List: 05000272/LER-1983-013, Forwards LER 83-013/99T-0.Detailed Event Analysis Encl 05000272/LER-1983-013-99, /99T-0:on 830215,calculated Moderator Temp Coefficient (Mtc) Value for All Control Rods Withdrawn Found More Positive than Tech Spec Allowance But within Expected Deviation.Limitation on Withdrawal Will Be Maintained
References
NUDOCS 8303140576
Download: ML20071D803 (4)

LER-1983-013, Forwards LER 83-013/99T-0.Detailed Event Analysis Encl

Event date:
Report date:
2721983013R00 - NRC Website

text

__

O psi 4G Public Service Electric and Gas Company P.O. Box E Hancocks B,-idge, New Jet sey 08038 Salem Generating Station March 2, 1983 Mr.

R.

Cp Haynes Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Haynes:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 83-013/99T Pursuant to the requirements of Salem Generating Station Unit No.

1, Technical Specifications, Section 6.9.2, we are submitting Licensee Event Report for Reportable Occurrence 83-013/99T.

This report is required within ten (10) days of the occurrence.

Sincerely yours, lcl,52fbwJ H. J. Midura General Manager -

Salem Operations RF:ks CC:

Distribution 9

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o Report Number:

83-013/99T-0 Report Date:

03-01-83 Occurrence Date:

02-15-83 Facility:

Salem Generating Station Unit 1 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Reactivity Control Systems - Moderator Temperature Coefficient -

Out-of-Specification.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 2 - RX Power 0 % - Unit Load 0 MWe.

DESCRIPTION OF OCCURRENCE:

At 1139 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.333895e-4 months <br />, February 14, 1983, during startup of Salem Unit 1, the reactor was taken critical, Mode 2 was entered, and zero power physics testing was commenced.

Results of the All Rods Out (ARO) Mcderator Temperature Coefficient (MTC) measurements showed a value of +0.30 delta k/k/gis MTC value is more positive than the maximum of 0 pcm/ F.

T F required by the Technical Specifications.

With the completion of zero power physics testing at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />. February 15, 1983, Limiting Conditi'on for Operation 3.1.1.4a and the associated action statement applied.

Control rod withdrawal limits were calculated and implemented February 15, to insure the MTC remains negative until the MTC value for the all rods withdrawn condition returns to within specification.

APPARENT CAUSE_OF OCCURRENSE:

Due to core design, beginning of life ARO MTC values are typically close to the specification limit and become more negative with increased fuel burnout.

The calculated value of +0.30 pcm/ F is within expected deviation from the design beginning of life value, which was slightly negative.

ANALYSIS OF OCCURRENCE:

The limitations on MTC are provided to ensure that the value of this coefficient remains within.the limiting condition assumed in the accident and transient analyses.

The MTC values required are applicable only to the plant conditions specified; surveillance of the MTC at the beginning and near the end of the fuel cycle is adequate to confirm that the MTC remains within limits.

8

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LER 83-013/99T-0,

f ANALYSIS OF OCCURRENCE: (cont'd)

Action Statement 3.1.1.4a requires:

With the MTC more positive than 0 delta k/k/ F for the all rods withdrawn, beginning of cycle life, hot zero thermal power condition, operation in Modes 1 and 2 may proceed provided:

1.

Control rod withdrawal limits are esthblished and maintained sufficient to restore the MTC to less positive than 0 delta k/k/ F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

These withdrawal limits shall be in addition to the limits of Specification 3.1.3.6.

2.

The control rods are maintained within the withdrawal limits established above until a subsequent-calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.

3.

A Special Report is prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.

CORRECTIVE ACTION

As noted, necessary control rod withdrawal limits were immediately implemented, in compliance with the action statement.

Control rod limits are summarized in Attachment 1; the limits apply through a burnup of 500 MWD /MTU.

This report is submitted in accordance with the Technical Specification 6.9.2.

FAILURE DAIA:

Not Applicable Prepared By R.

Frahm I

(Nb d

'G'ederal Manager -

Salem Operations SORC Meeting No.87-024

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