ML17275A968
| ML17275A968 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/30/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Ferguson R WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| NUDOCS 8104030568 | |
| Download: ML17275A968 (12) | |
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Docket No. 50-397 Washington Public Power Supply System ATTN:
Mr.
R. L. Ferguson Managing Director 3000 George Washington Way P. 0.
Box 968
- Richland, Washington 99352 Dist t Docket File LB41 Rdg DEisenhut BJYoungblood DLynch MRushbrook RTedesco>>'Vollmer TMurley DRoss RHartfield, MPA VNoonan OELD OIE (3)
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SUBJECT:
REQUEST FOR ADDITIONAL It<FORMATION ON THE ENVIRONMENTAL QUALIFICATIONS OF THE WNP-2 EQUIPMENT In the course of our review of your application for an operating license for the WNP-2 facility, we have identified a need for additional information on the environmental qualifications of the safety-related equipment in this plant.
The questions are contained in the enclosure.
Our tentative schedule for the site visit of the Seismic Qualification Review Team (SQRT) for your facility is during the week of October 5, 1981.
Accordingly, you should respond to this request for additional information in early September of this year.
We anticipate selecting the equipment which SORT will review about one week after receipt of your response and would expect you to provide the information requested in the "Qualification Summary of Equipment" forms within one week after that (i.e.,
two weeks before the site visit).
Since we are presently trying to confirm the timing of our various site visits, we request that you inform us whether you can support the WNP-2 schedule discussed above.
In addition, please forward one copy of all your responses on this matter to:
t1r. Richard Rahl EGSG Idaho, Inc.
P. 0.
Box 1625 Idaho Falls, Idaho 83401 OFFICEP SURNAME/
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If you have any questions on this matter, please contact the Project Manager, H. D. Lynch, at 301/492-8413.
Sincerely,
Enclosure:
As stated Robert L. Tedesco, Assistant Director for Licensing Division of Licensing cc:
See next page OFFICE)
SURNAME/
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Mr.
R.
L. Ferguson Managing Director Washington Public Power Supply System P.
0.
Box 968 3000 George Washington Way
- Richland, Washington 99352 ccs:
Nicholas Reynolds, Esq.
Debevoise 5 Liberman 1200 Seventeenth
- Street, N.
W.
Washington, D.
C.
20036 Richard Q. Quigley, Esq.
Washington Public Power Supply System P. 0.
Box 968
- Richland, Washington 99352 Nicholas Lewis, Chairman Energy Facility Site Evaluation Council 820 East Fifth Avenue Olympia, Washington 98504 Mr. 0.
K. Earle Licensing Engineer P.
0.
Box 968
- Richland, Washington 99352 Mr. Albert D. Toth Resident Inspector/WPPSS-2 NPS c/o U.
S. Nuclear Regulatory Commission P.
0.
Box 69
- Richland, Washington 99352
270.0, ENVIRONMENTAL QUALIFICATION BRANCH 271.1 Seismic and Dynamic Load Qualification 271.01 In accordance with the requirements of General Design Criteria (GDC) 2 and 4 of Appendix A to 10 CFR Part 50, all safe-.y-related equipment is required to be designed to withstand the e-fects of earthquakes and dynamic loads from normal operation, majntenance',
testing and postulated accident conditions.
GDC 2" further requires that such'equipment be designed to withstand appropriate combinations of the effects of -normal and accident conditions with earthquake loads.
271.02 The criteria which we will use to determine the acceptability of your equipment qualification program for seismic and dynamic loads are IEEE Std. 344-1975 as supplemented by Regulatory Guides 1.92 and 1.100 and Sections 3.9.2 and 3.10 of the Standard Review Plan.
Accordingly, indicate the extent to which the equipment in the
>lNP-2 facility meets these requirements and the above require~ient to combine seismic and dynamic loads.
For equipment which do~s not meet these requirements, provide justification for the use of)other criteria.
P Provide a list of all safety-related systems inclu>ling a list of all safety-related equipment and support structure<
associated with each system.
The equipment lists should indicate whether the equip-ment is supplied either by the nuclear steam suppl.
system vendor or by the architect/engineer for the balance of plant.
These lists should encompass all safety-related mechanical components, electrical, instrumentation, and control equipment, including ~alve actuators and other components such as active pumps and valves.
271.03 For each piece of safety-related equipment, provide the following information:
1.
State the method of qualification used:
a ~
b.
If byanalysis or test, indicate the compa the report, tl e reference report number an publication.
If by test, describe whether it was a sing' that prepared
.date of the
~
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e or multi-c ~
d ~
frequency test and whether the forcing function was single axis or multiaxis.
If by analysis,* describe whether static or'~'dp..amic, single or multiple-axis analysis was used.
Indicate the natural frequency (or frequeni;,ies) of the equipment.
271-1
'2.
Indicate whether the equipment has met the appropriate qualif-cation requirement".
3.
Indicate whether the equipment is required for:
(a} hgt stand-by; (b) cold shutdown; (c} both; or (d) neither.
4 ~
5.
Indicate the location of the equipment (i.e., the building and the elevation within the building).
State the availability for inspecti.on (e.g.,
whpther the equip.-
ment is already installed at the plant site}.
6.
Provide a compilation of the required response spectra (or time history) and the corresponding damping for each seismic and dynamic load specified for the equipment, including all other dynamic loads considered in the qualification.
Indicate, your method of combining all loads.
Identify all equipment which may be affected by fatigue deca,to vibration and describe your methods and criteria to,qualify, this equipment for such loading conditions.
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[i Describe the results of any in-plant tests, such as Kin situ impedance
- tests, and any operational tests you have planned tq co~nirm the qualification of any item of equipment.
To con'firm the extent to which the safety-related eeuipment of the WNP-2 facility meets the requirements of GDC 2 and 4, the Seismic
(}ualification Review Team (S(}RT) will conduct a plane site review.
For selected equipment, S(}RT will review the combined required response spectra (RRS) or the combined dynamic respo ise and examine the equipment configuration and mounting.
On this basis, S(}RT will then determine whether the test or analysis which ha 'een conducted demonstrates compliance with the RRS if the equipmen:
was qualified by test or'he acceptable analytical criteria if qua.,ified by analysis.
The staff requires that a "(}ualification Sugary *of [;quipment" as shown on the attached
- pages, be prepared for each seep ected piece of equipment and submitted to the staff two weeks pr"or to the plant site visit.
In this regard, you should make availab e at the plant site for SqRT review, all the equipment.
After the visit, you should then be prepared to submit certain selected document~
and reports.
for further staff review.
271-2
SAMPLB ualification Summar of E ui ment I.
Plant Name:
1.
Uti 1 ity:
2.,
NSSS!
3.
A/E:
. PWR BMR 1.
Scope:
[ ] NSSS 2.
Model Number:
3.
Vendor:
E ] BOP quantity:
4.
If the component is a cabinet or panel, nai. e "and model No. of >e devices included:
S.
Phys ica 1 Descri pt i on a.
Appearance b.
Dimens i ons c.
Meight 6.
Location:
Building:
Elevation:
7.
Field Mounting Conditions [
3 Bolt (Mo, Si'ze
)
- f. ]
8.
a.
System in which located; b.
Functional
Description:
c.
Is the equipment "required for
[
3 HotIu Standby
[ ]
Coltlghutdo m L ]
Boti 9.
Pertinent Reference Design Specifications:
[ ]
Ncaa.r 12/80 271-3
SAHP L
E III. Is Equipment Available for Inspection in the Plant:
" j Yes IV.. Equi pment qua 1 ifi cat ion Hethod:
I. ]
t1o I: j Test gualification Report*:
(No., Title and Date)
Company that Prepared Report:
Company that Reviewed Report:
( ],Analysis
( ] ('-ombination of Test
<nd Analysis
~I V.
Vibration Input:
1.
Loads considered;
- a. [ ] Seismic only
- b. [ ] Hydrodynamic only c.
I: ] Combination of (a) and gb) 2, Nethod of Combining RRS:
L ] Absolute Sum
( ] SR.'5
,8 3.
Required
Response
Spectra (attach the graphs):
4.
Damping Corresponding to RRS:
08E 3
3.
~other, speci>y}
=
SSE S/S
=
F/B
=
F/8
=
5.
Required Acceleration in Each Direction:
L 3.2PA
[ ] Other speci Ty /
V
=
V =
6..
Mere fatigue effects or other vibration loads cons1dered7 L]Yes I:]No If yes, describe loads qualification program:
considered and how they wer>>. treated in overall Aw'Awww&% ~
- NOTE: If more than one report coaylete items IV thru VII )'r each report.
12/80 271-4
SAMP L
E 3
If gual ifi cat i on by Test, then Compl etc~'.
1.
f 3 Single Frequency 2.
f ] Single Axis f ] Multi-Frequency:
f ] Multi-Axis 3.
No. of gualification"Tests:
4.. Frequency Range:
5.
Natural Frequencies in Each Direction (Side/Side, Front/Back, Vertical):
S/S
=
F/B
=
6.
Method of Determining Natural Frequencies f ] Lab Test
[ ] In-Situ Test 7.
TRS enveloping RRS using Multi-Frequency Test
[ 3 Analysis f.
Yes (Attach, TRS
& RRS gi aphs
[ ))No 8.
Input g-level Test:
OBE S/S
=
SSE S/S
=
9.
Laboratory Hounting:
[ j Bolt (No.,
Size
)
F/B F/B f ] Weld (Length
)
3 10.
Functional operability verified:, [
3 Yes
[ ]
No'1.
Test Results including modifications made:
[
3 Not Applicable 12.
Other test performed (such as aging or fragility.'est, including results j:
- Note: If qualification by a combination of test and<analysis also complete Item VI.I.
12/80 Cf 271-5
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P SAh1P LE VII. If gualification by Analysis, then complete:
1.
Nethod of Analysis:
L ] Static Analysis 3 Equivalent Static Analysis 2 ~
~ [ ] Dynamic Analysis:
[ ] Tirre-History
[ ] Response Spectrum Natural Frequencies in Each Direction (Side/Side, Front/Back, Vertical):
s/s
=
F/B
=
V =
3.
Nodel Type:
5 j 30
[32D
[ ] Finite Element
[ ] Beam 4.
[ ] Computer Codes:
r J1D
$ j Closed Form Snlunon Frequency Range and Ho. of modes considered:
[ 3 Hand Calculations 5.
Nethod of Combining Dynamic Responses:
[ -] Abs'o ute Sum f 3 SRSS
[
3 Otheg:
g gspeclTy) 6.
Damping:
OBE SSE Basis for the d mping used:
7.
Support Considerations in the model:
8.'ritical Structural Elements:
Governing Load or Response Sei smi c Total Stress A,
Identification Location Combination Stress Stress Allowable B.
Nax. Critical Deflection Location
'00'W W Naxiaurr< Al1owable Deflecti on to As su";i e F unct iona l Opera-bility f I
p 12/80 271-6
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