ML19224B838
| ML19224B838 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear, Crane  |
| Issue date: | 05/10/1979 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19224B836 | List: |
| References | |
| NUDOCS 7906270038 | |
| Download: ML19224B838 (2) | |
Text
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"889 9*a UNITED STATES NUCLIAR REQULATORY CCWMitSICM f
n REGICN IV i
ell RYAN POZA DRIVE, $UlTE 1000 F
ARUNGTON, TMXA8 M011
%**.a*/
May 10, 1979 MEMORANCUM FOR:
E. L. Jordan, A0 for TP, ROI, IE FRCH:
G. L. Madsen, Chief, R0&NS Branch, IE, RIV
SUBJECT:
RESULTS OF INSPECTION EFFORT FOR TI2595/03 The inspectitn effort for section III items A through E of TI2595/03 has not yet been conpleted.
he licensee expects to have completed setpoint i
changes, precedural changes, and cperator training by May 12, 1979.
This date will probably not be met.
Regicn IV will continue to follow the licensee's progress.
The ccmpletion of the required licensee's actions will be documented in a subsequent inspection report.
Reglen IV's ccnnents on the licensee's response to IES79-053 (attachment 1) are as fo11cws:
Item 1 - Develecmnt and revision of procedures for Natural Circulation, and Engineer.d Safety Features Actuaticn.
The ifcensee has altered his c:nnitted ccepletion time for procedural development and revision from that of previous responses (e.g., prior to exceeding 200o F RCS temperature in respcnse to IES79-05A) to prior to exceeding 5". rated power frcm the current refueling outage.
Item 2 - Modification _of. actions required in Item da and 1b of IES79-05A to account for M integrity.
The licensee intends to add the following guidance for securing HPI in addition to that given in Item 2:
3)
The RCS pressure returns to contal cperating pressure with [eo/b
- ne temperature in the hot and cold legs being controlled C7(,
with at least 50F subccoling by an cperable steam generator.
Note that section 4b.3 above allcws securing HPI for reasons other than preventing the plant frcm entaring an unsafe condition based cn RV integrity.
Mcwever, we feel that this section does not contradict the requirements of the bulletin, and provides additional guidance to the cperator over the range of all possible break sizes.
Itri 4
- nstitute a crccat manual reac:cr trio for transients that ratuit in RCS oressure increase.
254 166 79062700 N '
E. L. Jordan May 10, 1979 The licensee's decisions not to implement a prcrapt reactor trip for loss of offsite power and low pressurizer level Tre contrary to the requirecents of Item 4.
A decision as to their acceptability will have to be mde. ScoV Item 6 - Notification of NRC within one hour _ of the time that the reactor is not in a controlled or expected contition.
The licensee in this reponse did not specifically address the gne hcur ti e requirement for notificaticn.
M" Afex o G. L. Madsen Chief Reactor Operations and Nuclear Support Branch Region IV
Contact:
R. G. Spangler, 334-2781 or W. Jchnsen, RIP. 501-968-2290
Attachment:
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254 M