ML20213E066
| ML20213E066 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/03/1982 |
| From: | Speis T Office of Nuclear Reactor Regulation |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0484, CON-WNP-484, TASK-2.K.1, TASK-TM NUDOCS 8203190163 | |
| Download: ML20213E066 (3) | |
Text
.
A.
l Act /
l blAR 3 1982 Bc JPJ77 MEMORANDUM FOR: Robert L. Tedesco, Assistant Director for Licensing Division of Licensing FROM:
Themis P. Speis, Assistant Director for Reactor Safety Division of Systems Integration
SUBJECT:
ADDENDUM TO UNP-2 SAFETY EVALUATION REDORT, FC TER 7, INSTRUMENTATION AND CONTROL SYSTEMS Plant Name: WNP-2 p'
Ya Docket No.: 50-397 EECUWED Licensing Stage: 0L Responsible Branch: LB 12 G-l' R.101982ia-
-4 Project Manager:
R. Auluck N Am namn es m, l
ICSB Reviewer:
J. Knight /J. Rosenthal fI$""
S 6
Review Branch: ICSB j
Consultants: Savannah River Plant g
e, l
Review Status: Complete (6 Open Items)
L/
s TNI Action Plan Item II.K.l.23, Reactor Vessel Level Instrumentation, was not explicitly discussed in our SER of February 16, 1982. A discussion of this item for inclusion in Chapter 22 of the SER is attached.
I j
Reactor vessel level instrumentation is reviewed in conjunction with our j
review of Sections 7.2, 7.3, 7.4, 7.5, 7.7 of the FSAR and is discussed in Sections 7.2.2.6 and 7.5.2.4 of our SER of February 16,1982.
i j
Ong!nal Signed ljy Themis P. Speis i
Themis P. Speis, Assistant Director for Reactor Safety l
Division of Systems Integration ii
Enclosure:
l As stated DISTRIBUTION:
f Docket File cc: See attached list ICSB Reading File T. Speis J. Rosenthal (PF)
WNP-2 Subject File
Contact:
J. Rosenthal, ICSB X29459 f,o
. hlWlbS Y
m
, ICSB/DSk
.I.csazp.sI. b. g, f...l w a y!.
...l sga on'(,..,
.\\ g,,,,
j, j.
l o"" >
.l.
l; JRosenthal:c m od4 FRosa i
o.uk!3/ - /82 l3/2 /82 3/ '2_ /82 3/ 0,/82 I
8203190163 820303 T
c "r
ADOCK05000g7 OFFICIAL RECORD COPY GF
s R. Tedesco.
cc:
R. Mattson F. Rosa C. Rossi T. Dunning J. Knight J. Rosenthal R. Capra A. Schwencer R. Auluck A. Hadden (Savannah River Plant)
J. Elsbergas (ANL)
I I
I i
I i
4 i
l' omer)!
w nauty DaTE) uneroamsi. io..o.unc oz.
OFFICIAL RECORD COPY
Item II.K.l.23 Reactor Vessel Level Instrumentation Discussion and Conclusions The applicant has summarized the reactor vessel level instrumentation used at WNP-2 in response to TMI Action Plan Item II.K.l.23, Amendment 17, July 1981. The instruments that sense the water level are differential pressure devices calibrated for accuracy at a specific vessel pressure and liquid temperature condition. This instrumentation is extensively detailed in the General Electric Company Report NED0-24708, " Additional Information Reluired for NRC Staff Generic Report on Boiling Water Reacters," and has been re-viewed by us and evaluated in NUREG-626, " Generic Evaluation of Feedwater Transients and Small-Break Loss-of-Coolant Accidents in GE-Designed Operating Plants and Near-Term Operating License Applications." Vessel level instru-mentation is further discussed in Section 7.2.2.6, Failures of Vessel Sensing Lines Common to Control and Protection Systems, and Section 7.5.2.4, Vessel Level tieasurement Errors, of this report. We find this acceptable for this item.
l l
<