ML20206C500: Difference between revisions

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#REDIRECT [[IR 05000416/1987002]]
{{Adams
| number = ML20206C500
| issue date = 04/02/1987
| title = Revised Page 2 to Insp Rept 50-416/87-02,correcting Typos
| author name =
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| addressee name =
| addressee affiliation =
| docket = 05000416
| license number =
| contact person =
| document report number = 50-416-87-02, 50-416-87-2, TAC-61930, NUDOCS 8704130070
| package number = ML20206C486
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 1
}}
See also: [[see also::IR 05000416/1987002]]
 
=Text=
{{#Wiki_filter:, ,
    .                                                                                APR 0 01987
      Corrected Page 2                              2
      April 2, 1987
      5.
              Review of Test Results and Witnessing of Core Stability Testing
            The inspector performed a review of Technical Special Test Instruction
              IJ11-86-002-0-S. The test
                                            setup was reviewed and the methodology of
              stability testing was discussed with ORNL and ANFC representatives. A
            meeting was held to discuss the sequence of testing. A determination was
            made that two test points out of the original five suggested would not be
            tested due.to core limitations.
            The test placed the reactor in -:onditions corresponding to regions of the
            power-flow map with estimated decay ratios of 0.6 to 0.9. The test measured
            actual core stability and compared it to the predicted values. Data was
            taken on GETARs for later analysis and with ORNL equipment for real time
            analysis    of core stability.
            it was for data gathering only.The test did not have acceptance criteria, as
                                                                                  ~
                                                The results of the test are to-be the basis
            for determination of possible future operating restrictions for the reactor.
            L.  Phillips, Section Leader, RSB/ DBL /NRR, was also present to witness -
            testing.
                                                                ~
                                                        ~
                                                          .- -
            Stability measurements taken dc fng the testing at the selected test points
            ranged from decay ratios .0.09.t0.03 at 100% power and 100% flow to
            0.28 0.15 at 52% power and 39% flow. In order to obtain one flow / power
            point,
            flow map.the reactor had to be taken temporarily into Region IV of the power
                          Stability in this region
            noving through Region IV showed actual decay ratios ofbased upon measurementl
                                                                        0.31 0.10. The decay
            ratios  measured    at
            ratios of 0.6 to 0.9.  the time of testing were  well below the estimated decay      )
          Within the areas inspected no violations or deviation were identified.
                                                                                                  l
                                                                                                  l
                                                                                                  I
      8704130070 870402
      PDR    ADOCK 05000416                                  .
      G                    PDR
}}

Latest revision as of 21:27, 12 January 2021

Revised Page 2 to Insp Rept 50-416/87-02,correcting Typos
ML20206C500
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 04/02/1987
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20206C486 List:
References
50-416-87-02, 50-416-87-2, TAC-61930, NUDOCS 8704130070
Download: ML20206C500 (1)


See also: IR 05000416/1987002

Text

, ,

. APR 0 01987

Corrected Page 2 2

April 2, 1987

5.

Review of Test Results and Witnessing of Core Stability Testing

The inspector performed a review of Technical Special Test Instruction

IJ11-86-002-0-S. The test

setup was reviewed and the methodology of

stability testing was discussed with ORNL and ANFC representatives. A

meeting was held to discuss the sequence of testing. A determination was

made that two test points out of the original five suggested would not be

tested due.to core limitations.

The test placed the reactor in -:onditions corresponding to regions of the

power-flow map with estimated decay ratios of 0.6 to 0.9. The test measured

actual core stability and compared it to the predicted values. Data was

taken on GETARs for later analysis and with ORNL equipment for real time

analysis of core stability.

it was for data gathering only.The test did not have acceptance criteria, as

~

The results of the test are to-be the basis

for determination of possible future operating restrictions for the reactor.

L. Phillips, Section Leader, RSB/ DBL /NRR, was also present to witness -

testing.

~

~

.- -

Stability measurements taken dc fng the testing at the selected test points

ranged from decay ratios .0.09.t0.03 at 100% power and 100% flow to

0.28 0.15 at 52% power and 39% flow. In order to obtain one flow / power

point,

flow map.the reactor had to be taken temporarily into Region IV of the power

Stability in this region

noving through Region IV showed actual decay ratios ofbased upon measurementl

0.31 0.10. The decay

ratios measured at

ratios of 0.6 to 0.9. the time of testing were well below the estimated decay )

Within the areas inspected no violations or deviation were identified.

l

l

I

8704130070 870402

PDR ADOCK 05000416 .

G PDR