ML20064L256: Difference between revisions

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{{#Wiki_filter:.23 NUC PR ARMS, 1520 CST 2-C T. G. Campbell, 1760 CST 2-C G. L. Paulk, NRC T. L. Chinn, BFN TMICOPY TO NRC      C. W. Crawford, 670 CST 2-C Feb. 8, 1983        A. W. Crevasse, 401 USB-C G. S. Harrison, Plt Supt Office k p, .
U. S. Nuclear RegulatorF Commission
                                                - M            L. M. Mills, 400 CST 2-C SpiftEngineer Region II                                                Z. Szczepanskiy 417 UBB-C 101 Marietta Street, NW                              [C.Thomison,Ein Suite 3100                                          D. L. Williams, i'10B85C-K Atlanta, Georgia 30303 BFRO-50-296/8307 Reported under Technical Specification    6.7.2.a.2 Date of Occurrence: 2/7/83      Time of occurrence: 1415          Uni 3 Technical Specification Involved: 3.1.A                                  2 m
Conditions Prior to Occurrence 1          Unit 1 - maintenance outar,e                                            .
Unit 2 - refuel outage                                                    3 Unit 3 - 1100 MWe                                                        w Identification and Descriotion of Occurrence During performance of SI 4.1.A.7 , Reactor Low Water Level, switches LIS-3-203B and LIS-3-203D (switches No. 1) were found out of technical specification limits. The greatest out-of-tolerance was 0.74 percent.
Anoarent Cause of Occurrence The level indicating switches calibrat. ions had drifted.
Other Related Events BFRO-50-259/77002, 78024, 80087, 81001, 81071, 82016, 82084 260/80004, 81055, 81068, 82006 296/80028, 81055, 82005, 82011, 82049 Corrective Action Taken or Planned The switches were recalibrated, functionally tested and returned to service. The switches will be replaced with analog transmitter / trip unit system at a later date.
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            .  . Jones
          . wer Plant Superintendent Browns Ferry Nuclear Plant CO
                                                                            .cc  e 8302150167 830200 PDR ADOCK 05000296
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Latest revision as of 13:38, 6 January 2021

Telecopy Ro:On 830207,reactor Low Water Level Switches Found Out of Tolerance.Caused by Instrument Drift.Switches Recalibr,Tested & Returned to Svc.Switches Will Be Replaced W/Analog Transmitter/Trip Unit Sys at Later Date
ML20064L256
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 02/08/1983
From: Jones G
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8302150167
Download: ML20064L256 (1)


Text

.23 NUC PR ARMS, 1520 CST 2-C T. G. Campbell, 1760 CST 2-C G. L. Paulk, NRC T. L. Chinn, BFN TMICOPY TO NRC C. W. Crawford, 670 CST 2-C Feb. 8, 1983 A. W. Crevasse, 401 USB-C G. S. Harrison, Plt Supt Office k p, .

U. S. Nuclear RegulatorF Commission

- M L. M. Mills, 400 CST 2-C SpiftEngineer Region II Z. Szczepanskiy 417 UBB-C 101 Marietta Street, NW [C.Thomison,Ein Suite 3100 D. L. Williams, i'10B85C-K Atlanta, Georgia 30303 BFRO-50-296/8307 Reported under Technical Specification 6.7.2.a.2 Date of Occurrence: 2/7/83 Time of occurrence: 1415 Uni 3 Technical Specification Involved: 3.1.A 2 m

Conditions Prior to Occurrence 1 Unit 1 - maintenance outar,e .

Unit 2 - refuel outage 3 Unit 3 - 1100 MWe w Identification and Descriotion of Occurrence During performance of SI 4.1.A.7 , Reactor Low Water Level, switches LIS-3-203B and LIS-3-203D (switches No. 1) were found out of technical specification limits. The greatest out-of-tolerance was 0.74 percent.

Anoarent Cause of Occurrence The level indicating switches calibrat. ions had drifted.

Other Related Events BFRO-50-259/77002, 78024, 80087, 81001, 81071, 82016, 82084 260/80004, 81055, 81068, 82006 296/80028, 81055, 82005, 82011, 82049 Corrective Action Taken or Planned The switches were recalibrated, functionally tested and returned to service. The switches will be replaced with analog transmitter / trip unit system at a later date.

l l

. . Jones

. wer Plant Superintendent Browns Ferry Nuclear Plant CO

.cc e 8302150167 830200 PDR ADOCK 05000296

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