ML19260D569
| ML19260D569 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, Sterling  |
| Issue date: | 02/05/1980 |
| From: | STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | |
| Shared Package | |
| ML19260D563 | List: |
| References | |
| NUDOCS 8002110433 | |
| Download: ML19260D569 (2) | |
Text
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V ENCLOSURE k
SUPPLEMENTAL SNUPPS REPORT ON POTENTIAL DEFICIENCY:
QUALIFICATION OF CONTROL SYSTEMS Westinghouse identified the following four control systems for generic consideration of non-safety grade / safety grade interface interactions:
a.
Steam generator oower operated relief val"e control system, b
Pressurizer power operated relier valve control system.
c.
Main feedwater control system.
d.
Automatic rod control system.
SNUPPS notified the NRC I&E Recian I office of a potential significant deficiency involvino the above systems which, if subjected to an adverse environment, could impact the safety analyses and the adequacy of the pro-tective functions performed by safety grade equipment. The status of the resolution of these ootential deficiencies is as follows:
Item a.
The SNUPPS pressure controllers and main steam line atmospheric relief valve have been procured as Class IE devices and are environmentally qualified to withstand the effects of a high energy pipe break. There are no unresolved safety concerns regarding this issue.
Item b.
The SNUPPS pressurizer PORV is currently being redesigned to meet Class IE requirements and will be IEEE 323 qualified to the environment inside containment including high energy line breaks. SNUPPS is currently reviewing this design modification to assure that there are no unresolved safety concerns regarding this issue.
Item c.
Regarding the main feedwater control system on SNUPPS, Westing-house will revise WCAP-9230 to include the control and protection interaction scenarios and the Model F steam generator design parameters. The revised analysis in the next revision of WCAP-9230 will demonstrate that sufficient operator action time (greater than 30 minutes) exists before cortective action must be taken to inject auxiliary feedwater into the intact steam generators to prevent core uncovering. This ana'vsis will demon-strate that there are no unresolved safety concern regarding this issue.
Item d.
The SNUPPS power range ex-core detectors and associated in-containment equipment are currently being qualified, per WCA.P-8587 definition of seismic and environmental conditions, to the bounding steamline break conditions. Successful qualification of these detectors ensures proper operation of the control system following
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80 02110 433
Enclosure Page Two SLNRC 80-such incidents.
If total qualification proves imprac'1 cal, these detectors will be qualified to a steamline break envelope tempera-0 ture of 200 F and additional analyses will demonstrate that the high containment pressure set point (6 psig) is reached prior to exceeding 0
200 F inside containment. This analysis will demonstrate that there are no unresolved safety concerns regarding the automatic rod control system.
Upon completion of the described analyses and qualification programs, appro-priate revisions will be made to the SNUPPS FSAR.
The schedule for completion of these activities has not been established.
.ne1 1'l s.