ML19305D511: Difference between revisions
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fd C SNUPPS Standardiaod Nucteer Unit Power Plant System 5 Chobe Cherry Road | fd C SNUPPS Standardiaod Nucteer Unit Power Plant System 5 Chobe Cherry Road Nicholas A. Petric.k Enecutise Director Roch vitie, Maryland 20850 13011 86 %8010 March 20,1980 t | ||
SLNRC 80- 12 FILE: 0491.10.2 SUBJ: | |||
Undetectable Failure in Engineered Safety Features Actuation System Mr. Boyce Grier Director, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Penns Ivania 19406 Docket Nos. : STt 0-48&, STN 50-483, STN 50-485, STN 50-486 | |||
Safety Features Actuation System | |||
Mr. Boyce Grier Director, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Penns Ivania | |||
==Reference:== | ==Reference:== | ||
(1) SLNRC 79-21, dated 12/6/79: | |||
(2) Westinghouse letter (T.M. Anderson). NS-TMA-2204, to USNRC (V. Stello, Jr.), dated 2/15/80: | Same subject (2) Westinghouse letter (T.M. Anderson). NS-TMA-2204, to USNRC (V. Stello, Jr.), dated 2/15/80: | ||
Same subject i | |||
==Dear Mr. Grier:== | ==Dear Mr. Grier:== | ||
Reference (1) reported a potential deficiency involving the Engineered Safety Features Actuation System and described a test sequence that was the necessary corrective action applicable to the SNUPPS plants. | |||
Reference (1) reported a potential deficiency involving the Engineered | Ref-erence (2) provided the NRC with revised tests that yield more conclusive results. | ||
Safety Features Actuation System and described a test sequence that was the necessary corrective action applicable to the SNUPPS plants. Ref-erence (2) provided the NRC with revised tests that yield more conclusive results. | The SNUPPS utilitics are investigating hardware changes that may preclude the need for the tests described in Reference (2). | ||
The SNUPPS utilitics are investigating hardware changes that may preclude the need for the tests described in Reference (2). If.such hardware changes are not feasible, the appropriate test sequence from Reference (2) will be incorporated in the procedures for the SNUPPS plants. | If.such hardware changes are not feasible, the appropriate test sequence from Reference (2) will be incorporated in the procedures for the SNUPPS plants. | ||
Very truly yours | Very truly yours, | ||
/ | |||
/ | |||
-C %( | |||
Nicholas A. Petrick RLS/vas cc: | f Nicholas A. Petrick RLS/vas cc: | ||
Mr. James G. Keppler, Director, Region III, USNRC Mr. Karl V. Seyfrit Director, Region IV, USNRC Mr. Victor Stello, Jr., Director, Office of Inspection and Enforcement, USNRC, Washington D.C. | |||
800.4150179}} | 800.4150179}} | ||
Latest revision as of 05:34, 2 January 2025
| ML19305D511 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, Sterling  |
| Issue date: | 03/20/1980 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8004150179 | |
| Download: ML19305D511 (1) | |
Text
.
fd C SNUPPS Standardiaod Nucteer Unit Power Plant System 5 Chobe Cherry Road Nicholas A. Petric.k Enecutise Director Roch vitie, Maryland 20850 13011 86 %8010 March 20,1980 t
SLNRC 80- 12 FILE: 0491.10.2 SUBJ:
Undetectable Failure in Engineered Safety Features Actuation System Mr. Boyce Grier Director, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Penns Ivania 19406 Docket Nos. : STt 0-48&, STN 50-483, STN 50-485, STN 50-486
Reference:
(1) SLNRC 79-21, dated 12/6/79:
Same subject (2) Westinghouse letter (T.M. Anderson). NS-TMA-2204, to USNRC (V. Stello, Jr.), dated 2/15/80:
Same subject i
Dear Mr. Grier:
Reference (1) reported a potential deficiency involving the Engineered Safety Features Actuation System and described a test sequence that was the necessary corrective action applicable to the SNUPPS plants.
Ref-erence (2) provided the NRC with revised tests that yield more conclusive results.
The SNUPPS utilitics are investigating hardware changes that may preclude the need for the tests described in Reference (2).
If.such hardware changes are not feasible, the appropriate test sequence from Reference (2) will be incorporated in the procedures for the SNUPPS plants.
Very truly yours,
/
/
-C %(
f Nicholas A. Petrick RLS/vas cc:
Mr. James G. Keppler, Director, Region III, USNRC Mr. Karl V. Seyfrit Director, Region IV, USNRC Mr. Victor Stello, Jr., Director, Office of Inspection and Enforcement, USNRC, Washington D.C.
800.4150179