ML19345F230
| ML19345F230 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/27/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Mcgaughy J MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 8102130007 | |
| Download: ML19345F230 (9) | |
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NUCLEAR REGULATORY COMMISSION i
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s Docket Nos.: EO-416/417
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Mr. J. P. McGaughy, Jr.
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Assistant Vice President - Nuclear Production Mississippi Power and Light Company P. O. Sox 1640 Jackson, Mississippi 39205
Dear Mr. McGaughy:
SUBJECT:
REQUEST FOR INFOR'MTION CONCERNING EQUIPMENT QUALIFICATION FOR SEISMIC AND HYDRODYNAMIC LOADS g GRAND GULF NUCLEAR STATION As you are aware, a reevaluation of the original qualification adequacy of selected safety related equipment will be performed by our Seismic Qualification Review Team (SQRT).
In order to proceed with our review, we require certain information regarding your program used to qualify electrical and mechanical equiprent for dynamic inputs (seismic and hydro-l dynamic loads). The specific information required is identified in the enclosure to this letter.
Upon receipt of adequate responses to items 1 through 8 of the enclosure, we will select the equipment to be reviewed and schedule a visit to the Grand Gulf site.
As we are conducting these reviews with the assistance of our contract personnel at EG&G/ Idaho National Engineering Laboratory, we request that one copy of all responses be sent to:
Mr. Richard Rahl EG&G Idaho, Inc.
P. O. Box 1625
~
Idaho Falls, Idaho 83401 Please contact us if you desire any clarification of the enclosed request.
Sincerely, er; 3;*f.jj. 4.rc.
Robert L. Tedesco, Assistant Director for Licensing i
Division of Licensing
Enclosure:
As stated.
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cc: See next page.
l 8102180cco n i_,,
JAN 2 7 1981 cc:
Rccert b.
.cGehee, Esq.
Wise, Carter, cr.11c, 5;een c Ccrauay P. C. Scx 6ti Jacksco, hississippi 192C5 Tecy C. Conner, Jr., Esc.
Conner, Mccre 5 Corber 1747 Pennsylvania Avenac, N....
Washing:cn, D. C.
iLul't Mr. Acrian Zaccaria, Prc;ect Enta:eer Granc Gulf Nuclear Sta:1on Cechtel Pcuer Ccrpcration Gaithersburg, Narylanc 207t0 hr. Alan G. Wagner, Resident Inspec:cr P. C. Box 469 Por Gibson, hississippi 39150 Mr. N. L. Stampley, Sr. '.' ice Presicent Engineering, Prccucticn & Construction P.O. Cox 1640 Jackson, Mississippi 39205 Er. L. F. Dale Nuclear Prcject Aanager P.0 Scx 1640 Jacxson, Mississippi 39205 Mr. Jchn Richardscn P. O. Box 1640 Jackson, Mississippi
- e105 Mr. Richard Rahl EG&G Idaho, Inc.
P. O. Box 1625 Idaho Falls, Idaho 83401 i
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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION 1.
Pursuant to General Design Criterion 2, safety-related structures, systems and components are to be designed for appropriate load combinations arising from accidents and severe natural phenomena. With regard to the vibratory loads attributed to the feedback of hydrodynamic loads from the pressure suppression pool of the containment, the staff requires that safety-related mechanical, electrical, instrumentation and control equipment be designed and qualified to withstand effects of hydrodynamic vibratory loads associated with either safety relief valve (SRV) discharge or LOCA blowdown into the pressure suppression containment combined with the effects of dynamic loads arising from earthquakes.
The criteria to be used by the staff to detemine the acceptability of your equipment qualification program for seismic and dynamic loads are IEEE Std. 344-1575 as supplemented by Regulatory Guides 1.100 and 1.92, and Standard Review Plan Sections 3.9.2 and 3,10.
State the extent to which the equipment in your plant meets these requirements and the above requirements to combine seismic and hydrodynamic vibratory loads. For equipment that does not meet these requirements provide justification for the use of other criteria.
2.
Provide the following information:
(i) Two summary equipment lists (one for NSSS supplied equipment and one for BOP supplied equipment). These lists should include all safety related mechanical components, electrical, instrumentation, and control equipment, including valve actuators and other appurtenances of active pumps and valves.
In the lists, the following information should be specified for each item of equipment.
(1) Method of qualification used:
a) Analysis or test (indicate the company that prepared the report, the reference report number and date of the publication).
b) If by test, describe whether it was a single or multi-frequency test and whether input wac single axis or multi-axis.
c) If by analysis, describe whether-static or dynamic, single or multiple-axis analysis was used. Provide natural frequency (or frequencies) of equipment.
(2)
Indicate whether the equipment has met the qualification l
requirements.
l (3) Indicate the system in which the equipment is located and whether the equipment is required for:
l a) hot stand-by b) cold shutdown c) both d) neither-
- (4) location of equipment, i.e., building, elevation.
(5) Availability for inspection (Is the equipment already installed at the plant site?)
(ii)
An Acceptabile scenario of how to maintain hot stand-by and cold shutdown based on the fo'owing assumptions:
(1) SSE or OBE (2) Loss of offsite power (3) Any single failure (iii) A compilation of the required response spectra (RRS) for all applicable vibratory loads (individual and combined if required) for each floor of the nuclear station under consideration.
3.
Identify those items of nuclear steam supply system and balance-of-plant equipment requiring reevaluation and specify why reevaluation is necessary (i.e. because the original qualification used the single frequency, single axis methodology, because equipment is affected by hydrodynamic loads, or because both of the above conditions were present) for each item of equip-ment.
4.
Describe the methods and criteria used to determine the acceptability of the original equipment qualification to meet the required response spectra of item 2. (iii).
5.
Describe the methods and criteria used to address the vibration fatique cycle effects on the affected equipment due to required loading conditions.
6.
Based on the methods and criteria described in items 4 and 5, provide the results of the review of the original equipment qualification with identification of (1) equipment which has failed to meet the required response spectra and required requalification, and (2) equipment which was found acceptable, together with the necessary information to justify
~~
the adequacy of the original qualification.
7.
Describe procedures and schedule for completion of each item identified in item 6.(1) that requires requalification.
8.
Describe plans for a confirmatory in-situ impedance test and an in-plant SRV test program or other alternatives to characterize the ability of equipment to accommodate hydrodynamic loading.-
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, 9.
To confirm the extent to which the safety related equipment meets the requirements of General Design Criterion 2, the Seismic Quali-fication Review Team (SQRT) will conduct a plant site review. For selected equipment, SQRT will review the combined required response spectra (RRS) or the combined dynamic response, examine the equipment configuration and mounting, and then determine whether the test or analysis which has been conducted demonstrates compliance with the RRS if the equipment was qualified by test, or the acceptable analytical criteria if qualified by ar lysis.
The staff requires that a " Qualification Summary of Equipment" as shown on the attached pages be prepared for each selected piece of equipment and submitted to the staff two weeks prior to the plant site visit.
The applicant should make available at the plant site for SQRT review all the pertinent documents and reports of the qualification for the selected equipment. After the visit, the applicant should be prepared to submit certain selected documents and reports for further staff review.
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o Qualification Summary of Equioment I.
Plant Name:
Type:
1.
Utility:
PWR 2.
NSSS:
3.
A/E:
BWR I
l II. Component Name 1.
Scope:
[ ] NSSS
[ ] B0P 2.
Model Number:
Quantity:
3.
Vendor:
4.
If the component is a cabinet or panel, name and model No. of the devices included:
5.
Physical Description
- i. Appearance b.
Dimensions c.
Weight 6.
Location: Building:
Elevation:__,
7.
Field Mounting Conditicas [ ] Bolt (No.
, Size
)
[] Weld (Length
)
[]
8.
a.
System in which located:
I b.
Functional
Description:
Is the equipment required for [ ] Hot Standby [] Cold Shutdown c.
[] Both
[] Neither 9.
Pertinent Reference Design Specifications:
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2-III. Is Equipment Avcilable for Inspection in the Plant: [] Yes
[] No IV. Equipment Qualification Method:
[ ] Test
[ ] Analysis
[ ] Conbination of Test and Analysis Qualification Report *:........._........___.._____...___...
(No., Title and Date)...____.... _______.. ______..._...
Coreany that Prepared Report:,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
Corpany that Reviewed Report:,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
V.
Vibration Input:
1.
Loads considered:
- a. [ ] Seismic only
- b. [ ] Hydrodynamic only
- c. [ ] Combination of (a) and (b) 2.
Method of Combining RRS: [ ] Absolute Sum [ ] SRSS
[]
. n7.n e e, c a a.r.i ty)
.r s
3.
Required Response Spectra (attach the graphs):
4.
Darping Corresponding to RRS: OBE SSE 5.
Required Acceleration in Each Direction:
[] IPA
[ ] Other(specifyJ---
l OBE S/S =
F/B =
Y=
- =
SSE 5 / S =~ ~ ~ ~ - --- -- -- ~ ~ ---- F /B =~ ~ - ~ ~ - - --- ---- -- -- -- - V =- --- ----
6.
Were fatigue effects or other vibration loads considered?
[ ] Yes
[ ] No If yes, describe loads considered and how they were treated in overall qualification program:
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- NOTE: If more than one report conplete itens IV thru VII for each report.
{
1 2/ 80 I
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_3-VI.
_I_f _Qua_l_i fi c_a_t_i on__by Te_s_t_, t_he_n__C_o_mpl e_t_e* :
[ ] random 1.
[ ] Single Frequency
[ ] Mt.lti-Frequency: [ ] sine beat
[]~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - -
2.
[ ] Single Axis
[ ] Multi-Axis 3.
No. of Qualification Tests:
OBE___________SSE_________Othm 4.
Frequency Range:
5.
Natural Frequencies in Each Direction (Side / Side, Front /Back, Vertical):
S/S =
F/B =
V=
6.
Method o' Determining Natural Frequencies
[ ] Lab Test
[ ] In-Situ Test
[ ] Analysis 7.
TRS enveloping RRS using Multi-Frequency Test [ ] Yes (Attach TRS & RRS graphs:
[ ] No 8.
Input g-level Test: OBE S/S =
F/B =
V=
SSE S/S =
f/B =
V=
9.
Laboratory Mounting:
1.
[ ] Bolt (No.__,,
Size _ _ ) [ ] We 1 (Length _
)
[]__,
- 10. Functional operabilit. nrified:
[ ] Yes [ ] No
[ ] Not Applicable
- 11. Test Results including - difications made:
- 12. Other test performed (such as aging or fragility test, including results):
- Note:
If qualification by a codination of test and analysis also conplete Item VII.
12/80
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-4 VII. If Qualification by Analysis, then complete:
1.
Method of Analysis:
[ ] Static Analysis
[ ] Equivalent Static Analysis
[ ] Dynamic Analysis:
[ ] Time-History
[ ] Response Spectrum 2.
Natural Frequencies in Each Direction (Side / Side, Front /Back, Vertical):
S/S = _____._________.
F/B =_____..___..____.
V =__________________
3.
Model Type:
[ ] 3D
[ ] 2D
[ ] 1D l
[ ] Finite Element
[ ] Beam
[ ] Closed Form Solution 4.
[ ] Computer Codes:....__________.____.__..__._______________________________
Frequency Range and No. of modes considered:,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
[ ] Hand Calculations 5.
Method of Combining Dynamic Responses:
[ ] Absolute Sum [ ] SRSS
[ ] Other:
6.
Latis for the damping used:
7.
Support Considerations in the model:,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
8.
Critical Structural Elements:
Governing Load or Response Seismic Total Stress A.
Identification Location Combination Stress Stress Allowable Maximum Allowable Deflection l
B.
Max. Critical to Assure Functional Opera-j
..e.f.l.e_c_t_i on _
.L_oc_a.t.i o.n
.b.i.l.i t_y D.
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12/80 b.