ML20114B242
| ML20114B242 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/23/1985 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| KMLNRC-85-041, KMLNRC-85-41, NUDOCS 8501290003 | |
| Download: ML20114B242 (3) | |
Text
"
e KANSAS GAS AND ELECTRIC COMPANY THE ELECTRC COMPANY GLENN L MOESTER weCE P.EleDENT = NWCLEAR January 23, 1985 Mr. Harold l<.
Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Ocmuission Washington, D.C.
20555 KMLNRC 85-041 Re:
Docket No. SIN 50-482 Ref:
1.
SLNRC 84-047, dated 3/21/84, fran N.A. Petrick, SNUPPS, to H.R. Denton, NRC.
2.
SLNRC 83-019, dated 4/15/83, from N.A. Petrick, SNUPPS, to H.R. Denton, NRC Subj : FSAR Changes Relating to RVLIS High Volune Sensor Qualification
Dear Mr. Denton:
Enclosed is a clarification to the Envirormental OJalification Program described in the SNUPPS Final Safety Analysis Report for your review prior to issuance of the Operating License. Tnis clarification was requested by the NBC arx1 reflects the schedule indicated in the referenced letters.
This change will be incorporated into the first annual update of the Wolf Creek Final Safety Analysis Report. The information is hereby incorporated into the Wolf Creek Generating Station, Unit 1, Operating License Application.
Yours very truly, fuY G enn L. Koester Vice President - Nuclear GLK: tac Attach xc: PO'Connor HBundy 8501290003 850123 gDRADOCK 05000482 po l PDR 9l 201 N. Market -Wichita, Kansas - Mail Address: RO. Box 208 I Wichita, Kansas 67201 - Telephone: Ares Code (316) 261-6451
r..
SNUPPS V
To provide the required accuracy for level measurement, temperature measurements of the impulse lines are provided.
These measurements, together with existing reactor coolant temperature measurements and wide-range RCS pressure, are employed to compensate the d/p transmitter outputs for differences in system density and reference leg density, particularly during the change in the environment inside the containment structure following an accident.
Additional information (i.e., analyses, evaluations) concerning the Westinghouse generic reactor vessel level instrumentation system has been submitted to the NRC via Reference 7.
The specific hardware for SNUPPS is not exactly as documented in Reference 7, since the SNUPPS design does not include a measurement of reactor vessel level above the hot legs.
However, the analyses, evalua-tions, and conclusions contained in Reference 7 are appli-cable to SNUPPS, since they are not sensitive to the above-mentioned design difference.
Ihl$tKT ---+-Thermocouple / Core Cooling Monitor System The core cooling monitor system is a core exit thermo-couple / core cooling detection system which provides presen-tation and display of the status of the core heat removal capability to both the plant operators _and the technical support center.
The system consists of redundant channels and output trains of. thermocouple measurements, wide-range -
hot-and cold-leg RTD temperatures, and reactor pressure signals.
These parameters are used by the system to display thermocouple temperatures and to calculate satura-tion temperatures and margin of saturation (Tsat margin),
which is often referred to as subcooling.
The calculations are performed by the system which is based on microproces-ser and data handling devices.
Thermocouple Monitor The core exit thermocouple portion of the ICC system is arranged as-follows:
i (a)
Primary' system The primary system measures all the thermocouples via isolators. located in the qualified backup system cabinet.
(b)
Backup system The backup system consists of two channels, each moni-The toring half of the 50 core outlet thermocouples.
system has separation and redundancy as well as quali'-
fication to ~ comply with Appendix B of NUREG-0737 (see the discussion of item 4 below).
PCi-9 18.2-61b 8
I
4 o
. INSERT Environmental qualification of the reactor vessel level instrumentation system high volume sensor will be completed prior to restart following the first refueling outage at each of the SNUPPS plants.
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