ML20010J219
| ML20010J219 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 09/22/1981 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-81-110, NUDOCS 8109290725 | |
| Download: ML20010J219 (3) | |
Text
T SNUPPS Standardized Nucteer Unit Power Plant System 5 choke cherry Road Nicholas A. Petrick Rockville, Maryland 20060 Executive Director (301) 869 8010 September 22, 1981 SLNRC 81-110 FILE: 0541 LU I /r cn SUBJ:
ASME Code Cases
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's Mr. Harold R. Denton, Director!
'g[q v., g@0 8 ' "i ' U,h Office of Nuclear Reactor Regulation
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U. S. Nuclear Regulatory Commission 4n Washington, D. C. 20555
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O Docket Nos. STN 50-482, STN 50-483, and STN 50-486
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Dear Mr. Denton:
The SNUPPS FSAR 3ddresses (in Appendix 3A) compliance to Regulatory Guides 1.84 and 1.85.
FSAR Section 5.2.1.2 addresses code cases used for Class 1 components'in the reactor coolant pressure boundary.
In discussions with the NRC staff, a specific list of code cases was requested.
The attached information provides the specific Class 1 code case usage and will be incorporated in the next FSAR Revision.
Very truly yours, E.%C Nicholas A. Petrick RLS/mtk Attachment cc:
J. K. Bryan UE D. F. Schnell UE G. L. Kcester KGE D. T. McPhee KCPL g oI W. A. Hansen NRC/ CAL T. E. Vandel NRC/WC de 8109290725 810922-PDR ADOCK 05000482 A
PDR J
SNUPPS (Ref. 2) of the use of Code Case 1528 have been submitted to thu NRC.
j 5.2.2 OVERPRESSURE PROTECTION RCS overpressure protection is accomplished by the utiliza-tion of pressurizer safety valves along with the reactor protection system and associated equipment.
Combinations of these systems provide compliance with the overpressure requirements of the ASME Boiler and Pressure Vessel Code,Section III, Paragraphs NB-7300 and NC-7300, for pressurized water reactor systems.
Auxiliary or emergency systems connected to the RCS are not utilized for the prevention of RCS overpressurization protection.
5.2.2.1 Design Bases Overpressure protection is provided for the RCS by the pressurizer safety valves which discharge to the pressurizer relief tank by means of a common header.
The transient which establishes the design requirements for the primary system overpressure protection is a complete loss of steam flow to the turbine with operation of the steam generator safety valves and maintenance of main feedwater flow.
However, for tne sizing of the pressurizer safety valves, no credit is taken for reactor trip nor the operation of the following:
a.
Pressurizer power-operated relief valves b.
Steam line relief valve c.
Steam dump system d.
Reactor contrei system e.
Pressuri?.er level control system f.
Pressurizer spray valve For this transient, the peak RCS and peak steam system pressure must be limited to 110 percent of their respective design values.
Assumptions for the overpressure analysis include:
- 1) the plast is operating at the power level corresponding to the engineered safeguards design rating and 2) the RCS average temperature and pressure are at their maximum values.
These are the most limiting assumptions with respect to system overpressure.
5.2-2
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i INSERT A The specific code cases used for Callaway 1 and Wolf Creek were:
Steam Generator: 1484 and 1528 Pressurizer: 1528-3 (Wolf Creek) 1528 (Callaway 1)
P'.p ing : 1423-2
'/a t ve s : 1649, 1769, 1567 (Wolf Creek only), and N-3-10 i
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