ML19309B549
| ML19309B549 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, Sterling  |
| Issue date: | 02/05/1980 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| SLNRC-80-6, NUDOCS 8004040269 | |
| Download: ML19309B549 (2) | |
Text
7 I c_.
SNUPPS Stenderdized Nuclear IJnit Power Plant Systern 5 Choke Cherry Road Nicholas A. Petrick Rockvi% Maryland 20850 Executive Director (301) 869 8010 February 5,1980 SLNRC 80 6 FILE:
0491.10.2 SUBJ: Oualification of Control Systems Mr. Boyce Grier Director, Region I U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, Pennsy]vania 19405 Docket Nos:
STN 50-482, STN 50-483, STN 50-485, STN 50-486
/
Reference:
SLNRC-7'5, dated September 28, 1979, same subject
Dear Mr. Grier:
The referenced letter discussed a deficiency involving the qualification of certain control systems. The enclosure to this letter provides a supple-mental reoort on the same subject. The additional descriptions of analyses and qualification programs required for final resolution of this matter will be provided in revisions to the SNUPPS FSAR.
Ver,struly yours, t%C Nicholas A. Petric RLS/jdk Enclosure cc:
Mr,.- James G. Keppler, Director, Region III, USNRC
[Mr. Victor Stello, Jr., Director, Office of Inspection
- r. Karl V. Seyfrit, Director, Region IV, USNRC and Enforcement, Washington, D.C.
n 8004 0do 269 Y
1 l
ENCLOSURE SUPPLEMENTAL SNUPPS REPORT ON POTENTIAL DEFICIENCY:
QUALIFICATION OF CONTRDL SYSTEMS Westinghouse identified the following four control systems for generic consideration of non-safety grade / safety grade interface interactions:
a.
Steam generator power operated relief valve control system.
b.
Pressurizer power operated relief valve control system.
c.
Main feedwater control system.
d.
Automatic rod control system.
SNUPPS notified the NRC I&E Reaion I ;ffice of a potential significant deficiency involvina the above systems which, if subjected to an adverse environment, could imoact 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 pioe 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.
1 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 corrective action must be taken to inject auxiliary feedwater into the intact steam generators to prevent core uncovering. This analysis will demon-strate that there are no unresolved safety concerns regarding this issue.
Item d. -The SNUPPS power range ex-core detectors and associated in-containment equipment are currently beina qualified, per WCAP-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 followina
.