ML20031C524
| ML20031C524 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway, 05000586  |
| Issue date: | 10/02/1981 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM SLNRC-81-118, NUDOCS 8110070239 | |
| Download: ML20031C524 (4) | |
Text
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SNUPPS Standardized Nuclear Unit Power Plaat System 5 Choke Cherry Road Nicholas A. Petrick Rockville, Maryland 20850 Enecutive Director (301)8694010 October 2, 1981 SLNRC 81-118 FILE: 0541 SUBJ:
NUREG-0737, Item II.F.2 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Docket Nos. STN 50-482, SIN 50-483, and STN 50-586
Reference:
SLNRC 81-112, dated September 24, 1981: Same Subject
Dear Mr. Denton:
The referenced letter provided an FSAR change that described the SNUPPS instrumentation for detection of inadequate core cooling.
Per discussions with the NRC staff, additional information is provided in the enclosure. This information modifies that pro-vided in the reference.
Very truly yours, I
P_.h.<scQ y
Jicholas A. Petrick RLS/mtk C
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Page Six such that each of the redandant microprocessor systems has core exit temperatures distributed over the entire core, in sufficient number to determine the radial power distribution and so located as to verify power distribution symmetr>y among core quadrants.
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(b) Attachment 1, Item (2)
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The primary operator display is a computer based display and f{bf
-v calculation system.
It provides information as required by f'; q N,
subitems (a) through (f).
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(c) Attachment 1. Item (3)
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" j The back-up system to display thermocouple readings is located in a cabinet which also houses the core cooling monitor.Q q [f system has a 40-character (alphanumeric) display line locatedThis ba on the front of each of the microprocessor drawers.
5 up system can display all of the 50 individual thermocouple
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temperatyreswithfn6 minutes. The range extends from less l'
c,q than 200 to 2300 F.
{ y }n (d) Attachment 1, Item (4) ep Human-f actors consideration of the types and locations of dis-h.I piars and alarms is eiscussed in sections i8.i.is and i8.3.2.
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O The ICC instrumentation will be considered in the overall human factors evaluation.
-o (e) Attachment 1. Item (5) f Conformance to the speci'ic items of Appendix B to NUREG-0737 is as follows:
(1) Appendix B, Item (1)
The thermocouple / core cooling monitor instrumentation is l
currently being tested to establish environmental qualifica-tion in accordance with Regulatory Guide 1.89 (NUREG-0588).
This qualification requirement applies to the complete I
l instrumentation channel from thermocouple to display where l
display indicates the remote display, analog meter, and Qualified cnannel isolation devices isolate this recorder.
qualified instrument: tion from the data links, technical support center display, c9d plant computer display.
The seismic portion of the environmental qualification test-ing is being performed to comply with Regulatory Guide 1.100.
This seismic qualification will provide assunnce that the instrumentation still continue to read within the required accuracy followit,g, but not necessarily during, a safe shut-g down earthquake.
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(g) Attachment 1 Item (7)
The instrumentation qualification is discussed in item (4). e.1 above.
(h) Attachment 1, Item (8)
The instrumentation system is in conformance with this require-ment.
(1) Attachment 1, Item (9)
Quality assurance is discussed in item (4).e.5 above.
(5) he-ite-instrumentition-c:n p:rfe in-(ts-funct tes 4-dependent 4
-the phnt-caputer,
/ (6) The ICC instrumentation will be installed by fuel load.
(7) and (8) The Westinghouse Owners Group has developed ICC operating guidelines. These guidelines were developed using the generic ICC analyses discussed in Section 16.1.8.
These generic guidelines will be considered, as appropriate, by the SNUPPS utilities in developing plant spacific operating procedures.
I (9) No additional submittals are required with the exception of emer-f gency operating procedures discussed in Sections 18.1.8 and 18.1.15.
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