ML19319C418
| ML19319C418 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/05/1978 |
| From: | Fiorelli G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Seyfrit Kb NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19319C417 | List: |
| References | |
| NUDOCS 8002140798 | |
| Download: ML19319C418 (2) | |
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GLEN ELLYN, ILLINol$ 60137 May 5, 1978 MEMORANDUM FOR:
K. V. Seyfrit, Assistant Director for Programs Division of Reactor Operations Inspection, IE FROM:
G. Fiorelli, Chief, Reactor Operations and Nuclear Support Branch
SUBJECT:
POWER ASCENSION TESTING FOR REMOVAL OF BURNABLE POISON R0D ASSEMBLIES, DAVIS-BESSE 1 (AITS F30377H2)
During the initial startup and power ascension program at Davis-Besse 1, the licensee committed to a specific test program.
Because of the burn-able poison rod assembly (BPRA) problem, it may be necessary to change the original core and reactivity control configuration 1/
With the proposed changes to the core and reactivity control in mind, we have reviewed the licensee test original power ascension program to ascer-tain in our opinion what part of the test program should be repeated in whole or in part (or at least addressed by the licensee as to why it is not necessary to re-perform the testing). Partial justifir.ation to repeat some of the tests is that the change in core configuration represents a change in base line data. The attachment lists the licensee's tests by number and subject.
It is our recommendation that the licensee (through NRR) be asked to ad-dress each of~the items and either commit to retesting in whole, or in part, or support their conclusion as to why the testing need not be per-formed. This list does not include tests in the original ccamitment that have not yet been performed (it is assumed that these tests will be run as originally required).
1/ These changes were discussed in a meeting at HQ held May 2, 1978.
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G. Fiorelli, Chief Reactor Operations and Nuclear Support Branch
Attachment:
As stated cc w/ attachment:
H. D. Thornburg, IE J. H. Sniezek, IE IE Files Central Files 8002140 N (
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ATTACIDiENT RETESTING FOR REMOVAL OF BURNABLE POISON RODS DAVIS-BESSE 1 CYCLE 1-A TP -800.00 Power Escalation Sequences Modify procedure for new test program TP-800.02 Nuclear Instrumentation Calibration at Power Perform Phase II of the test verification of correct thermal power level and axial power inbalance.
TP-800.05 Reactivity Coefficients at Power Perform at 40%, 75% and approximately 100% F.P.
Values of each level should j
be extrapolated to F.P. to verify new predicted values.
TP-800.08 ICS Tuning at Powcr Performed at 40%, 75% and 100% to reverify that control rod responses are within previously determined control responses.
TP-800.11 Core Power Distributions Perform at 40%, 75% and 100%. Values at each power level should be extra-polated to F.P. to verify new predicted values.
The licensee should also clarify LER limitations (currently limits for LHR in the Test Procedures as nore restrictive than the Technical Specifications).
TP-800.14 Turbine / Reactor Trip Test The licensee should address whether the decrease in reactivity insertion tine from the Control Rods will change the unit response described in section 15.2.7 of the FSAR.
If systen respcuses are changed, a turbine trip from 75% would ba recommended before performance of the trip frem 100%.
IP-800.18 Power Inbalance Detector Correlation Test Perform at 40% - See TP 800.24 for additional comments.
TP-800.20 Rod Reactivity Worth Measurements The licensee should address why this test should not be repeated at 40%,
75%, 100% F.P. with the new control rod configuration.
TP-800.23 Unit Load Transient Test I
Perform at 40% to demonstrate that system responses have not been adversely j
changed.
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Attachment 2
May 5, 1978 TP-800.24 incore Detector Test With the new core configurations significant software changes will be re-quired for handling incore detector readout signals.
The licensee should address constant and/or correction applied to the detector signal includ-ing the method for handling failed detectors.
This test should be repeated at 40% F.P.
TP-800.28 Pseudo Ejected Rod Test Because the proposed operation involves operation with Group 7 CRA fully inserted and is a significant change from the previous base line data, this test should be repeated at 40% F.P.
It has been previously noted (Rancho-Seco Startup testing), that rod worth is greatly influenced by group insertien.
IP-800.31 Vibration and Loose Part Monitor Repeat at each power plateau to re-establish base line data and as a comparison to previous data.
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