ML20077F714
| ML20077F714 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000000 |
| Issue date: | 07/28/1983 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 83-0041, 83-41, NUDOCS 8308030011 | |
| Download: ML20077F714 (2) | |
Text
--
I, SNUPPS Stenderdized Nuclear Unit Power Plant Systern 5 Choke Cherry Road Nicholas A. Petrick Rockvisse, henrytend 2005o Exocutive Director (301) 8864010 July 28,1983 SLNRC 83- 0041 FILE:2 0278=
SUBJ:
Licer. sing Issues W R Harold 1R2 Denton, Directop Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Docket Nos. STN 50-482 and STN 50-483
Dear Mr. Denton:
The purpose of this letter is to provide information on two generic safety issues and to request the review status of several SNUPPS licensing reviews.
In response to a request by Mr. J. Holonich of the NRC, the SNUPPS design does not use Westinghouse type DB reactor trip breakers. The reactor trip breakers used in the SNUPPS design are type DS-416. Also, concerning the occurrence of control rod guide tube support pin failures at pressurized water reactors, the modifications will be effected at each SNUPPS plant to properly install improved support pins prior to fuel load.
Regarding the review status of licensing issues, the SNUPPS licensing issues listed below have been addressed in prior SNUPPS correspondence to the NRC.
A significant time period has elapsed without an indication from the NRC staff of the acceptability of the submitted information. All of the issues are confirmatory items (CI); the item numbers are for the Callaway Plant. The numbers in parentheses are for Wolf Creek Generating Station.
CI 9(B.10)
Operator Actions required to Maintain Safe Shutdown from outside the Control Room.
Information provided in letter SLNRC 83-004, dated February 2, 1983. FSAR was updated in Revision 11, dated March 10, 1983.
8308030011 830728 PDR ADOCK 05000482
\\
A PDR i o
o SLNRC 83- 0041 Page 2.
CI 11 (B.12)
Volume Control Tank Level Control and Pro-tection Interaction.
Information provided in FSAR Revision 10, dated September 30, 1982.
CI 13 (B.14)
Environmental Qualification of Control Systems.
Information provided in letter SLNRC 83-005, dated February 2, 1983.
FSAR was updated in Revision 11.
CI 28 (B.28)
Performance Testing of BWR and PWR Relief and II.D.1 Safety Valves.
Information provided in letter SLNRC 83-002, dated January 7, 1983.
CI 28 (B.28)
Justification of Use of Certain PORVs.
II.K. 3.11 NRC staff must review information provided by Westinghouse.
CI 36 (B.32)
Post-Accident Monitoring (Regulatory Guide 1.97,Rev.2).
Information provided in letter SLNRC 82-31, dated July 6,1982.
(NRC staff has indicated a review completion date of 2/84).
For these issues, SNUPPS requests that the current review status and projected review schedule be identified.
Very truly yours, f%c Nicholas A. Petric MHF/nld5b17 cc:
D. T. McPhee KCPL J. H. Neisler USNRC/ CAL G. L. Koester KGE
-H. Roberds/W. Schum USNRC/WC D. F. Schnell UE i
=
e-
,c.,
-