ML20028H239
| ML20028H239 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/14/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20028H240 | List: |
| References | |
| NUDOCS 9011190212 | |
| Download: ML20028H239 (2) | |
Text
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The licensee has committed to install an excore neutron monitoring system that meets the recommendations of R.G. 1.97.
The licensee has also agreed to provide the staff with quarterly updates of the progress of procurement, design, and installation of a qualified system.
Until the post-accident qualified neutron flux monitoring system is installed and operational, the licensee would use the presently installed neutron flux monitoring system and other post-accident qualified instrumentation. The presently installed system is expected to function during the initial phase of an accident (including a LOCA) to indicate suberitical reactor power.
Long term monitoring is available through the APRM channels where operator action is required at the APRM down scale alarm.
However, since the presently installed system is not fully qualified to R.G. 1.97, 1
Category I requirements, long-term monitoring in a harsh environment may not be directly available over the entire R.G. 1.97 range.
In this event, other measures and indications are available to the operator, as discussed below:
(a) The present control rod position indication system provides the reactor operator with the information that all rods are inserted.
(b) Qualified instrumentation, such as reactor pressure, suppression l-pool temperature and safety relief valve (SRV) actuation, provides the reactor operator with post-accident information of assessment of reactor power if direct neutron monitoring capability is not available.
1 (c) The Emergency Procedures (EP) are symptom based and provide appropriately conservative actions if reactor power can not be directly measured in a post-accident situation.
The EP contain action steps that mitigate the symptomatic effects of design basis events (such as LOCA), and beyond design basis events (such as ATWS).
The compensatory measures listed above ensure that the consequences of an accident previously evaluated will not be significantly increased by the absence of a post-accident neutron flux monitoring system during the fifth fuel cycle.
Based on the licensee's commitment to install an improved neutron flux monitoring instrumentation that fully conforms to R.G.1.97, Revision 2
- by startup following the fifth refueling outage and to provide quarterly reports on the status and schedule for procurement, design, and installation of the instrumentation, the staff concludes that the proposed delay is acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in a requirement with respect to the
' installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released off site, and that there is no significant increase in individual or cumulative l
9011190212 901114 PDR ADOa 0500041c I
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Attachment.
E01 shall complete the following requirements on the schedule noted below:
Enercency Response Facilities (Generic Letter 82-33, NbREG-0737 Surplement 1. 55ER e5 E01 shall implement the specific items below, in the rnanner described in MP&L letter (AECM-83/0232) datec April 15, 1983, as modified in MP&L letter i
(AECH-83/0486) dated August 22, 1983, no later than the following specified dates:
(a) Safety Parameter Display System (SPDS)
II) Submit a safety analysis and implemer.tation July 1985 plan to the hRC' (2l SPDS fully operational and operatur trained Prior to startup 1
fo11 ewing first refueling outage, (b) DetaileaControlRoomDesignReview(DCROR) y (1) Submit a prograra plan to the NRC December ICE 4
.(2) Submit a sunnary report to the NRC including July 1986 a proposed schedule for implementation
'l (c) Regulatory Guice 1.97 - Applic6 tion to Emergency Response facilities l
l (1) Submit a report to the NRC describirg how the February 1985 requirements of Supplement 1 to NUREG-0737 have been or will te met.
L (2)
Implement (installatien or upgrade)
Prior to startup I
l requirements of.R.G. 1.97 with exception following first
'I of flux monitoring.ano coolant level monitoring.- refueling outage.
(3)
Implement (installation or upgrace)
-Prior to startup requirements of R.G. 1.97 for coolant-level fellowing.second
)
ronitoring.-
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refueling outage.
i (4)- Imp 1tment (installation or upgrade)
Prior to startup i
L recuirements of R.G. 1.97 for flux monitoring.
following fifth l
refueling outage.
u-
-(d) Uperace Emergency Operating Procedures.(EOP's)
R L
i (1) Submit a Procedures Generation Package to the April 1985 NRC.
18 Amendment No. 72 a
1
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