ML20198G289
| ML20198G289 | |
| Person / Time | |
|---|---|
| Site: | Washington Public Power Supply System |
| Issue date: | 02/06/1975 |
| From: | Stello V Office of Nuclear Reactor Regulation |
| To: | Deyoung R Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-1038 NUDOCS 8605290421 | |
| Download: ML20198G289 (5) | |
Text
'
) >
(
, ~
/.3 0istribution~~~
iDReading cle'it7ITRs) 3f N' ..
L f
13h,,,4 t '
^
. p;g .3 E'. Leins i ,
& S13 Mos. 50 "460 Cocket for UR's, Group 1 tor Regulat '
Jr., Assistant o DirectorOffice f Nuclear Reac Richard C. BeYoung, JECTS NOS.1 & 4 4 jects Nos. 1 &
WASHINGTON NUCLEAR 1 3, T.Cox PROWashington Nu- '
PlantLicensing Stage:STN 50 460&
January 23,1975forProject Leader: Completion f Docket Nos.: Branch Responsible Date:
Date NecessaryNone Required Requested Completion ject:
Applicant's ResponseAction Planned of Response:
on ProNone Require been evaluated bycompliance Next Complete Description subject applicant ited has toSection Group 50.55a Review Status: he The SER review is limand Stand The PSAR submitted Co by tBranch. des ification stems the Reactorapplicant Systems with the Part 50, Seismic Class of the ining componentsdary and oth by the of those fluid conta coolant pressure of 10 CFR Classifications A is bounfinal SER evaluationenclo of the reactorsafety. f this branch to o N&w Hy important of review vu ,. Director the scope Assistant ulation Victor Stello, Jr.,for Reac
- Office
Enclosure:
SER i
[yl asu soe k )
y, Mcdonald, L e603290421 750206 ec: w/ enc 1 PDR ADocn osooo460 PDR .-
- s. Hanauer E
~~~~..
F. Schroe t' " ~~
y,, SchwenC** -
~
- . Cox ! t,*,RSB~~
VSt li . -
T, HoVaN L:RSBp d -
g ,, ..
.jarga ' ~ Rdriwood:db]
c f. 75
~
w /7s - g }.,,,,..
,,[",,. ,.i n * "" -
W
, WASHINGTON fl0 CLEAR FR0(ECTS 1 AND 4 DOCKET NOS. 50-460 AND S13 -
211.0 Quality Group Cla,ssification, Reactor Systems Branch 211.1 Seismic Classification _
(3.2.1) Structures, systems and components important to safety that are required to be designed to withstand the effects of a Safe Shutdown Earthquake ard remain functional have been properly classified as Seismic Category 1 items. These' plant features are these necessary to assure (1) the integrity of the reactor coolant pressure boundary, (2) the capability-to shutdown the reactor and maintain it in a safe shutdown
, condition, or (3) the capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10 CFR Part 100.
All other structures, systems and components that may be required for operation of the facility are designed to other than Seismic Categcry I requirements. Included in this classificaticr. are these pcrtions of Category I systems which are not required to perform a safety function. Structures, systems and components important to safety that are designed to withstand the effects of a Safety Shutdown Earthquake and remain functional have been identified in an acceptable manner in Table 3.2-2. .
The basis for acceptance in the staff's review has been conformance of the applicant's designs, design criteria and
- design bases for structures, systems and components important to safety with the Commission's regulations as set forth in General Design Criterion 2, and to Regulatorj Guide 1.29, Technical Staff Position, and Industry Standards.
The ~ staff concludes that structures, systems, and components important to safety that are designed in accordance with Seismic Category 1 requirements provide reasonable assurance that the plant will perfora in a manner providing adequate ,
safeguards of the.hcalth and safety of the public.
211.2 System Quality Gr ,up classification (3.2.2) Fluid system pressure-Fetaining ccmponents important to safety will be designed, fabricated, erected and tested to quality standards commensurate with the importance of the safety function to be performed. The applicant has applied the ANS
211.2 classification system (Safety Classes 1, 2, 3 and MS) dich corresponds to the Commissions Quality Groups A, B, C and D in Regulatory Guide 1.26 to those fluid containing comportents which are part of the reactor coolant pressure boundary and other fluid systems important to safety where reliance is placed on these systems: (1) to prevent or mitigate the consequences of accidents and malfunctions originating within.
the reactor coolant pressure boundary, (2) to permit shutdown of the reactor and maintenance in the safe shutdown condition, and (3) to contain radioactive material. These fluid systems have been classified in an acceptable manner in Tables 3.2-1 and 3.2-2 and on color codes system Piping and Instrunentation Diagrams, Figures 3.2-1 through 3.2 48. -
U The basis for acceptance in the staff's review has been con-formance of the applicant's designs, design criteria, and design bases for pressure-retaining components such as pressure vessels neat exchangers, storage tanks, pumps, piping and valves in fluid systems important to safety with the Co:rmission's Regulations set forth in General Design Criterion 1, the require-ments of the codes specified in Section 50.55a of 10 CFR Part 50, g and to Regulatory Guide 1.26, Technical Staff Positions, and Industry Standards.
- The staff concludes that fluid system pressure-retaining compo-
=
nents important to safety that are designed, fabricated,
, erected, and tested to quality standards in conformance with these requirements provide reasonable assurance that the plant will perform in a manner providing adequate safeguards to the
- health and safety of the public.
211.3 Compliance with 10 CFR Part 50, Section 50.55a 5 (5.2.1.3) Components of the reactor coolant pressure boundary as defined by the rules of 10 CFR Part 50, Section 50.55a have been properly identified in Table 5.2-1 and classified as ASME Section III, Code Class I components. These components within the reactor coolant pressure boundary will be constructed in accordance with the requirements of the applicable codes and addenda as
-~
specified by the rules of 10 CFR Part 50, Section 50.55a, Codes and Standards.
In meeting these requirements, the staff concludes that construc-tion of the components of the reactor coolant pressure boundary in conformance with the Commission's regulations provides reasonable assurance that the resulting quality standards are commensurate with the impcrtance of the safety function of the reactor coolant pressure boundary and is considered acceptable.
211.3 211.4 Applicable Code Cases (5.2.1.4) The specified ASME Code Cases in Table 5.2-2 whose re-quirements will be applied in the construction of pressure-retaining ASME Section III, Code Class 1, components within the reactor coolant pressure boundary (Qualt.j Group Classi-fication A), are acceptable to the Commission. The staff concludes that compliance with the requirements of these Code Cases in conformance with the Commission's regulations is expected to result in a component quality level commen-surate with the impor.tance of the safety function of the reactor coolant pressure boundary and is considered acceptable. .
9 4
e e
e 4
a w
c- ;
Bibliography .
/
-General References
- 1. 10 CFR Part 50, Appendix A General Design Criterion 1, " Quality Standards and Records."
- 2. 10 CFR Part 50, Appendix A, General Design Criterion 2, " Design Bases for Protection Against Natural Phenomena."
- 3. 10 CFR Part 50, Appendix B, " Quality Assurance Criteria for Nuclear
. Power Plants and Fuel Reprocessing Plants." ,
- 4. 10 CFR Part 100, Appendix A, " Seismic and Geologic Siting Criteria for Nuclear Power Plants."
- 5. Regulatory Guide 1.26, " Quality Group Classifications and Standards."
- 6. Regulatory Guide 1.29, " Seismic Design Classification."
- 7. ANSI H18.2, " Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants," American National Standards Institute (1973).
. 8. ASME Boiler and Pressure Vessel Code,1971 and 1974 Editione,Section III, " Nuclear Power Plant Components," American Society of Mechanical Engineers (1971 and 1974).
- 9. ASME Boiler and Pressure Vessel Code,1971 and 1974 Editions,Section VIII, Division 1, " Pressure Vessels," American Society of Mechanical Engineers (1971 and 19i4).
- 10. , ANSI B31.1-1973, " Power Piping," American National Standards Institute (1973).
- 11. API Standard 620,' Fourth Edition, February 1900, " Recommended Rules for Design and Construction of Large, Welded, Low-Pressure Storage
' Tanks," American Petroleum Institute (1970).
12 ', API Standard 650, Third Edition, July 1966, " Welded Steel Tanks for Oil Storage," American Petroleum Institute (1966).
- 13. AWUA D100-67, "AWWA Standard for Steel Tanks-Standpipes, Reservoirs, and Elevated Tanks for Water Storage," American Water Works Asso-ciation (1967).
- 14. ANSI B96.1-1967, " Specification for Welded Aluminum-Alloy Field-Erected Storage Tanks," American National Standards Institute (1967).
l-
_. - - ,