ML20127K192
| ML20127K192 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 05/30/1985 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | Goldberg J HOUSTON LIGHTING & POWER CO. |
| References | |
| GL-83-28, NUDOCS 8506270297 | |
| Download: ML20127K192 (29) | |
Text
F
.j S
Docket Nos. 50-498 and 50-499 Gy 3 01985 Mr. J. H. Goldberg Vice President - Nuclear Engineering and Construction Houston Lighting and Power Company Post Office Box 1700 Houston, Texas 77001
Dear Mr. Goldberg:
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION The NRC staff has determined that additional information is required in three subject areas related to Equipment Qualifications. The areas are:
1.
The Seismic Qualification Review Team (SQRT) audit.
2.
The Pump and Valve Operability Review Team (PVORT) audit.
3.
Items 4.1, 4.2.1 and 4.2.2 of Generic Letter 83-28.
Guidance on providing the required information on these subjects is contained in Enclosures 1 and 2. contains guidance on the SQRT and PVORT audits and Enclosure 2 on the Generic Letter 83-28 items.
Please let us know your schedule for responding to the above.
If you have any questions, please contact Dr. Prasad Kadambi at (301) 492-7272.
Sincerely, J5/
George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing
Enclosures:
As stated DISTRIBUTION Docket File NRC PDR Local PDR JLee NKadambi GWKnighton TMNovak Nf(
DL:LB#3 D/h NPKadambi:tm GI ton va k 05/29/85 05p/85 0
485 8506270297 850530 PDR ADOCK 05000498 A
/
South Texas Mr. J. H. Goldberg William S. Jordan, III, Esq.
. Group Vice President, Nuclear Harmon, Weiss & Jordan Houston Lighting and Power Company 2001 S Street, N.W.
P. O. Box 1700 Suite 430 Houston, Texas 77001 Washington, D. C.
20009 Brian Berwick, Esq.
Mr. J. T. Westermeir Assistant Attorney General Manager, South Texas Project Environmental Protection Division Houston Lighting and Power Company P. O. Box 12548 P. O. Box 1700 Capitol Station Houston, Texas 77001 Austin, Texas 78711 Mr. E.- R. Brooks Mr. Claude E. Johnson, Resident Mr. R. L. Range Inspector / South Texas Project Central Power and Light Company c/o U. S. NRC P. O. Box 2121 P. O. Box 910 Corpus Christi, Texas 78403 Bay City, Texas 77414 Mr. H. L. Peterson Mr. Jonathan Davis Mr. G. Pokorny Assistant City Attorney City of Austin City of Austin P. O. Box 1088 P. O. Box 1088 Austin, Texas 78767 Austin, Texas 78767 Mr. J. B. Poston Mr. A. Von Rosenberg Ms. Pat Coy City Public Service Board Citizens Concerned About Nuclear P. O. Box 1771 Power San Antonio, Texas 78296 5106 Casa Oro San Antonio, Texas 78233 Jack R. Newman, Esq.
Newman & Holtzinger, P.C.
Mr. Mark R. Wisenberg 1615 L Street, NW Manager, Nuclear Licensing Washington, DC 20036 Houston Lighting and Power Company P. O. Box 1700 Melbert Schwartz,Jr., Esq.
Houston, Texas 77001 Baker & Botts One Shell Plaza Mr. Charles Halligan Houston, Texas 77002 Mr. Burton L. Lex Bechtel Corporation Mrs. Peggy Buchorn P. O. Box 2166 Executive Director Houston, Texas 77001 Citizens for Equitable Utilities, Inc.
Route 1, Box 1684 Brazoria, Texas 77422
-Regional Administrator - Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011
- Mr. Lanny Sinkin Citizens Concerned About Nuclear Power 3022 Porter St. N. W. #304 Washington, D. C.
20008 Mr. S. Head HL&P Representative
. Suite 1309 7910 Woodmont Avenue Bethesda, Maryland 20814
Enclosure [
Guidance in Providing Information to Support the Review and Audit of the Seismic and Dynamic Qualification of Seismic Category I Hechanical and Electrical Equipment and the Pump and Valve Operability Qualification To confinn the extent to which safety-related equipment meets the requirements of the General Design Criteria (GDC) of 10 CFR Part 50, the NRC staff, assisted by Technical Assistance Contractors, will conduct a plant site audit and review.
It is our intent to conduct.a plant specific on-site Pump and Valve Operability Review Tean (PVORT) audit concurrent with the Seismic Ocalification Review Team (SCRT) audit. We believe such scheduling should minimize manpewer and scheduling conflicts for the applicant, the NRC staff, and our technicel assistance centractors.
Since the site audit is performec cr a sampling basis it is recessary to ensure that 25 to 90 percent of the safety related equipment are qualified and installed before the audit.
Ir. order that the staff is familiar with the seisric and dynanic qualification programs currently being conducted, it is recuested that all test crocrar:s be identified bv submitting a brief description cf the orncer.
items beina tested, the vendor'or the testing laboratory invclved. and the dates and location of the tests.
Infornation about the crgoing test prograns shculd be submitted as soon as possible so that the NRC staff can review and witress relevant tests for selected items.
A list of all safety-related equipr.ent should be prcvided se that an assessrent of the ecuipment qualificatien status can be mace by the staff.
Ecuionent shculd be divided first by system ther bv cerocnent type. Attr,chreet =1 shec a tabular fo-nat which ihnuld be followed te r*esent the status sumer of all srfety ralatec equi; rent.
. After the information on Attachment il is received, and it is determined that the equipnent qualification is substanti, ally complete, selections will be made of the equipment to be audited, and reviewed, by the SQRT Sp'ecific information on equipment. selected for audit by each and PVORT.
review team will be requested.
The infomation that will be requested for those equipment selected by the SQRT is shown in Attachment #2.
The information that will be requested for those equipment selected by PVORT is shewn in Attachment #3 In addition, the applicant will be requested to provide a complete set of floor response spectra identifying their 4
applicability to the equipment listed in Attachment #1.
Fer the equipment selected by the SQRT for audit, the combined Required Respense Spectra (RRS) or the combined dynamic response will be reviewed.
The SQRT-will examine and c mpare the equipment on-site installation v/s the test configuration and mounting, and determine whether the test. or analysis which has been conducted conforms to the applicable stendards and agrees with the RRS.
In cases where the plant is a BWR facility, t.he equipment qualifying. documentation must also provide evidence that the hydrodynamic loads in the (0 - 100) Hz frequency range have been accounted for.
For the equipment selected by the PVORT for audit, the applicant must provide evidence that appropriate manufacturers' test.5 have been conducted ireviewed, and approved, and that the equipment meets, or exceeds the design requirements.
The applicant must also provide qualification. test and or analysis results tha; provide assurance that the equipment will cperate (function) during and folicwing the Design Basis Events (D5E) and all appropriate ecmbinations thereof.
The specific information requested in Attachments #2, and f3 should be provided to the NRC staff two~ weeks prior to the plant site visit. The applicant should make available a.t the plant site 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.
The' purpose of i
the audits is to confirm the acceptability of the qualification procedures, and implementation.of the procedures to all safety-related equipment based on the review of a few selected pieces.
If a number of deficiencies are observed or significant generic concerns arise, the deficiencies should be removed for all eculoment important to safety subject to confirmation by a follow-up audit of randomly selected items before the fuel loading date.
The site audits will also' include a review of the extent to which the documentation of equipment qualification is complete. The acceptance criteria for requirements on records is provided in Section 3.iD-of the Standard Review plan Revision 2 (NUREG-800).
- i
, 4 ;
. j
,1 ATTA'CHMENT #1 t MASTER LISTING OF SEISMIC AND~QYNAMIC QUALIFICATION
SUMMARY
AND STATUS OF SAFETY-RELATED EQUIPMENT
8 ASSOCIRED EXPLANATORY NOTE I
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9 D e o m e
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htASTER LISTING OF S EISHIC NID DYNAMIC QUALIFICATlotl
SUMMARY
AND STATUS OF SAFITT,Y.lutATeb KanPNewfi..;[.
^
el.htl T IMMIL:
DU CKE7 NO:
UTILITY:
A/D N5SS:
I ov-la.
rAss FOR EQUIPMENT LIS TED DELOW rit u sus,pt.ing IS : Alli D, NSSS D, OTilER D.
Shl'lY SYSTEM & FUNCTION ARE ;
f}-
t>C t t r EpuoPM E5 p y E. 0 C A T
- 0 SS con $g?gggg> Wl '[,'fuY, lf, e GTATits RgS Coons Asso
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- *AL. gng,.
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ATTACHMENT (I' (Continued) i NOTES 70 MASTER LISTING i
(1) The information on Plant Name, Docket No., etc., are pertinent to i
the power station and will be the same for all sheets.
(2) The equipment is listed by supplier (circle one after " SUPPLIED SY:") and by system. (indicate name and function of system after
" SYSTEM AND FUNCTION:").
Typical safety systems, for example, are Engineered Safeguard Actuation, Reactor Protection, Containment
. Isolation, Steamline Isolation, Main Feedwater Shutdown and Isolation,"
Emergency Power, Emergency Core Cooling, Containment Heat Removal, Containment Fission Product Removal, Containment Ccabustible Gas Centrol, Auxiliary Feedwater, Containment Ventilation, Containment Radiation Monitoring.. Control Rosn Habitability System, Ventilation for Areas Containing Safety Equipment, Component Cooling, Service Water, Emergency Systems to Achieve Safe Shutdoan, Postaccident Sampling and Monitoring, Radiation Monitoring, Safety-Related Display Instrumentation.
The supplier will usually ha either A/E or NSSS.
Use separate sheets for each system.
Use additional sheets when a given systen has more equipment than can be listed on one sheet.
(3)
"ICENT. NO." is to be filled in by the organization preparing the list.
Each equipment listed should have separate identification number.
The following form is reconmended:
(a) Fcr A/E supplied equipment;, the number may be " BOP-XXX."
If more than one grcup is preparing for=s, the number may be
" SOP-M-XXX" (Mechanical) or " BOP-IC-XXX" (Instrumentation and Control).
~
~
(b) For NSSS supplied equipment, the number. may be NSSS-M-XXX, N SSS-I C-X'~
etc.
,(c) The numbe.r written on each line-(for each listed equipment) shculd be an ordered numeric listing for the above indicated-XXX (-001 through conpletion).
These numbers need not follow in order for each system (-002 and -004 may be with one system, but -003 may be with another system).
(d)
Inside the pare:ithesis should be 'the " BOP-M," "NSSS-IC," etc.
(4) The " TYPE" refers to its generic name, such as pressure transmitter, indicator, solenoid value, cabinet, etc.
Equipment type should be described by indicatine for era.;1e, motor driven pump, turbine driven pump, motor cperated valve, air operated valve,18" valve, etc. Following abbreviations can be used where appropriate.
Valves:
EV - Bali valve,. BP/ - Butterfly. valve, CV - check valva, OV - Diaphragm valve, GV - Gato valve, GLV - Glove valve, SV - Safety Valve, RV - Relief Valve Pumps:
CP - Centrifugal pump, P P - Positive displacement pump, DOP - Deep draft pu p, JP - Jet pudp-
(5)
Olantity refers to the number of the same equipment used in the plant.
(5)
Under mounting condition indicate the following as applicable:
CF for concrete floor mounting CW for concrete wall mounting DM for direct mounting H!! for hanger mounting EM for rack mounting ~
CM for cabinet mounting EM for equipment mounting Mounting details such as number of bolts, weld length, etc. need not be indicated here..
' (7)' The columns " SEISMIC" and "0THER DYNAMIC" need only b'e checked if applicable.
In the case of BWRs indicate "H" under "0THER DYNAMIC" column where qualification includes hydrodynamic loads.
(8)
Under " REQ'D INPUT (ZPA)," the applicable "g" level should be p rovid ed.
(g)
UnderTQualification Method under analysis, indicate "S" for static, and "D" for dynamic; under test frequency, indicate "SF" for single, and "MF" for multiple;' and under text direction, indicate "SD" for single, "MD" for multiple.
(1D) Equipment status is to be addressed separately to qualif.ication and to installation..
The applicable letter should be provided under the column headed
" QUAL," according to the following code:
.A The qualification and associated documentation are complete.
B The qualification testing is finished but associated documentation i
is not yet submitted or still in review.
C The qualification plan / proc'edure is decumented, but testing has not yet begun.
D Equipment to be qualified.
E Equipment is judged not qualifiable and will be replaced with qualified equipment.
i F
For EWR plants only:
Equipment is qualified for seismic loading enly.
Requalification will be performed to acccunt for the suppression pool hydrodynamic leading effects.
L
3-The applicable letter should be provided under the column headed
" INSTALLATION," according to the following code:
A Installation is ccmpleted.
Equipment is ready fer service.
Equipment mounting / hookup is completed, but significant parts B
of the equipment are not yet installed.
C Equipment is located at its intended service location, but mounting and/or hookup is not completed.
D The equipment is not installed and is not available for inspection.
(11) The Required Response Spectra (RRS) package shculd'be provided alcng with the liaster Listing.
Only response spectre applicable to the listed equipment shcald be included, each numbered for reference under the column headed "RRS REF."
will reference the same RRS.
In many cases, several equipme.)t (12) Codes and Standards Applicable codes, standards and Regulatory Guides should be indicated here, for example, ASME Section III Class 2; IEEE-344,.1975, 323-1974, 382-1972; ANSI N278-1, P.egulatory Guide 1.100, 1.148 etc.
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Attachment #2 M
Seismic and Dy' namic Qualification Sumary of Equipment
- To be completed to' stand on its own (do not refer to any document)
- All questions are to be answered (if not applicable; mark "N/A")
I.
Plant Name:
1.
Utility:
2.
Location:
3.
Type:
4.
Capacity (MWe Net):
5.
Containment Type:
6.
Cooling Source:
-7.
NRC Docket No.:
8.
CP Docket Date:
9.
NSSS Vendor:
- 10. A/E:
II.
Comconent Name:
1.
Scope:
[ ] NSSS
[
] BOP 2.
Vendor:
3.
Vendor Model No.:
4.
Manufacturer:
5.
Manufacturer Model No.:
6.
Purchase Spec. No.:
7.
Total No. in Safety ijstems:
8.
Location (Choi:se the worst one with respect to seismic) a.
Building:
b.
Elevation and Area:
c.
Ervironment:
[ ] Harsh
[
] Mild 9.
Field Mounting:
a.
[
] F1::or
[
] Wall
[
] Pipe
[ ] Panel
[
] Other (describe) b.
[
] Eolted; description:
'"*'9"*'*"*/
[
] Welded; description:
[ ]Other; description:
Mcunting restriction from the manufacturer, if any:
(horizontal c.
vertical,etc.)
10.
Functional Description of the Equipment:
a.
System in which located:
(for item 8 in 11, acove) b.
Type:
[
] Active
[
] Passive c.
Equipment recuired for: [
] Hot standby
[
] Colc shu:::own
[
] Both
[ ] Neitnsr d.
Intended safet'y function:
s e..
Direct consequences of its failure (brief description of the effect on the system):
f.
Redundancies, if any:
III.
Ecuiement Oualification Method:
[ ] Test
[ ] Analysis
[ ] Ccmbination of test & analysis
[
]Other(describe)
IV.
Loads and Load Combinations:
1.
Loads:
a.
[ ] Seismic b.
[
] Hydrodynamic c.
[ ] Flow induced vib.
c.
[
] Normal operation vib.
e.
[ ] Other dynamic loads: (specify) 2.
Combination technique:
3.
Required acceleratien in each direction:
a.
[
] ZPA
[ ]Other;specify:
b.
OBE:
s/s
- f/b
- v
SSE:
s/s
- f/b
- v
-V.
Qualification by Test (ccmolete this section for each recert includine cartial test):
1.
Test repert:
(Cempany) a.
Title:
no.:
- revision
- date
b.
Reviewed by:
2.
Qualificaticn re;:crt: (Ccapany) l a.
Title:
l l
no. :-
- revisien;
- date
I-b.
Reviewed by:
3.
Laboratory counting:
Describe [from shaker table to the ecuipment; include orienta icn, a.
bolt (size, no., gr., etc.), weld (type, size, length, electrode type,etc.)]:
b.
If different.from field mounting include equivalency justification:
4.
Resonance search:
[ ]yes
[ ] no
- a.. Technique:
b.I Excitation magnitude & frequency interval (or sweep rate):
c.
Resonances found: (up to:
)
s/s:
- f/b
- v
5.
Test
Description:
a.
Input:
(a)
[ ] single axis;
[ ] biaxial;
[ ]pseudobiaxial;
[
] tri-axial
[
] random;
[ ] sine beat;
[
] other:
[
] phase coherent;
[
] phase incoherent (b)
Frequency range:
(c)
Input level (g-level & frequency)
OSE:
s/s:
- f/b
- v
SSE:
s/s:
- f/b
- v
(d)
Number of tests performed:
OBE:
- SSE
- other
(e)
Sequential test, including fatigue & vibrat4cn aging conducted:
[
]yes
[ ]no Justification, if not performed:
b.
Output:
(a) TRS generated:
[
]yes
[
] no (b) Percent damping in TRS generation:
(c)
Percent damoing used in RRS:
(d) Margin included in RRS:
[ ] by test lab.
[ ] by others: (specify)
(e) Attach sets of TRS and RRS comparison plots (if not provided, explain):
.,w
c.
Results:
Basis of' qualification:
(a)
[
] structural integrity verified; [
l operability verified (b) Failures detected during qualification tests':
(c) Ancmalies (with disposition) if any:
(d) Modifications made (in the equipment or mounting) during the qualification phase; describe, if any:
(e). How (medifications) implemented in the field:
d.
Other tests performed (such as fragility test; include resuits)
VI.
Qualification by Analysis (ccmolete this section for each recort )
1.
Analysis Recort: (Ccmpany)
~~
a.
Title:
no.:
- revision
- date
'b.
Reviewed by:
2.
Qualification Report: (Ccmpany) a.
Title:
no.:
- revision
- date
3.
Failure modes:
4 Method of Analysis:
[
] static
[ ] static coefficient
[
] cynamic
[
] time history
[ ] response scectrum 5.
Natural frequencies (up to cut eff frequency of:
):
s/s:
- f/b
- v
,--,.,y_
6.
Model type:
[
] 1D;
[ ]2D;
[ ] 3D
[ ]. finite element: (kinds of elements used)
[ ] other: (specify) 7 '.
Support & Boundary conditions in the model:
8.
Ccmputer codes used:
Method of verification:
9.
Damping:
OBE:
- SSE
- Basis
10.
Fatigue & aging conside-stion:
[ ]yes
[
]no 11.
Responses:
a.
Method of combination:
[ ] ABS;
[ ]SRSS;
[ ] algebraic,
[ ]other,specify:
h b.
For critical elements:
A Total Source -
Calculated Allowable of Identification Location Loads Stresses Stresses Allowables Allow.
Source of Allow.
Iden'tification Location Loads Total Defl.
Defl.
Defl.
VII.
Surveillance and Maintenance Prcgram:
1.
Qualified life:
(caseo en weakest 11nx or appencage in :ne equip.)
2.
Basis:
3.
Crecedure of assuring operability of the equipment under saismic ano dynamic conditien thrcughout the plant life:
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e Atiiachment#3
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PUMP AND VALVE OPERABILITY ASSURANCE REVIEW 1.
PLANT INFORMATI0'l 1.
Name:
Unit No.
2.
Docket No.:
3.
Utility:
4 NSSS:
[]PWR[]BWR 5.
A' /E:
II. GENERAL COMPONENT
- INFORMATION 1.
Supplier: []NSSS [] BOP 2.
Location:
a.
Suilding/ Room b.
Elevation c.
System 3.
Component number en in-house drawings:
4 If compenent is a [] Pump co=plete 11.5.
Ifcp=penentis'a[]Valv6cc=pleteII.6.
5.
General Pume Data a.
Pump b.
. Prime-mover Name Name Mfg.
Mfg.
Model Podel
-5/N S/N Type '
Type l
l Ine comoonent, whether pt=p or valve, is censidered to be an assembly j
ccepcsed of the body, internals, prime-mover (or actuater) and funcu enal j
accessories.,
ll l
e
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Pump' (con"tinued) 6.
Prime-mover (continued) a.
Size Size' Weight-Weight Mounting Mounting Method Method Required B.H.'P.
N.P.
Parameter Desien O'oeratine-Power requirements:
(include normal, maximum and minimum).
Press Electrical Temp Flow Head Other Recuired NPSH at maximum If MOTOR list:
. flow Duty cycle Available NPSH Stall current Operating Speed Class of insulation Critical Speed
~
~
List functional accessories,:*
List control signal inputs:
Functicnal accesseries are these sub-ccmpenents not supplied by the manufacturer that are recuir-1 to make the pump assembly operatienal, 4
(e.g., coupling, lubricating.il system, etc.)
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_3 6.
General Valve Data a.
Valve b.
, Actuator (if not an integral
~
unit)
~~
Name
Name' i
Mfg.
Mfg.
Model Model S/N S/N Type Type Size
-Site Weight ~
' Weight Mcunting-Mounting Method ^
Method Recuired Torcue Tercue Parameter Desten.
'Oceratine Power' requirements:
(include normal, maximum and minimum).
Press Electrical Temp Flow
.MaxJPacrossyalve Closing time 9 max IP Other: [] Pneumatic [] Hydraulic Opening time 9 max IP Pow.r recuirements for functional at:essories, (if any) l List c:ntrol signal in;:uts:
\\
4 List-functional accessories:* '
III. FUNCTION 1
Briefly describe components normal and safety functions:
, 2.
The cceponents normal state is:
O Operating O Standby 3.
Safety function:
a.
O Emergency reactor b.
O Containment heat shutdown re:reval
,c.
O Containment isolation d.
O Reactor heat removal O Reactor core cooling f.
O Prevent significant e..
release of radio-active material to envircnment g.
O Does the compenent function to mitigate the consecuences of cne or :: ore of the following events? O Yes O No If "Yes", identify.
O LOCA C HELS
'O MSLS O Other 4.
Safety recuirements:
O Intermittent Operation O During postulated event O Centinucus Operatien O Following postulated event If'ccmpenent operation is recuired following an event, give approximate length of time component must remain operational.
(e.g., hours, days,etc.)
Functional accesseries are these sub-ccmpen.ents not supplied by the manufacturer that are recuired :
-(e.g., limit switches).
make the valve assembly cperational, 9
~
n - --- - - - -, - -
c-5-
E 5.
For VALVES:
does the cecponent
[] Fail open,.[] Fail closed
[] Fail,as is -
Is this the f ail safe position?
[] Yes
[]No Is 'the valve use'd for throttlirg purpcses?
[] Yes
[] No Is the valve part of the reactar coolant pressure boundary?
[] Yes
[] No Does the' valve have a specific limit for leakage? [] Yes []No If"Yes"'givelimit:
IV.
OUALIFICATION 1.
Reference by specific number those applicable sections cf the design codes and standards tpplicable to the component:
2.
Reference those cualification standards, used as a guide to
, cualify the ecmponent:
3.
Identify these parts of tre above cualification standards deleted or modifie5 in the cualif tcation program.
Deleted:
Mcdified:'
4.
Have acceptance criterias seen established and dccumented in the i
test plan (s) for the ce= potent? []Yes
[] No
- ' hat is t'he expected f ailure mode that wculd keep the pump er 5.
n valve assembly frcm performing its safety functien?
6.
Arc :ne cargins' identifitc in t.ke dualifica:icn cocumentaticn?
[]Yes
[] No I
d.
- argin is the difference between design basis parameters and the test
. parame:ers used fer eculpment cualification.
v.
e
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,n
.g.
5 If component is a PUMP, complete IV.,7.
- If component is a VALVE, complete IV.S.
7.
Pump operability has been demonstrated by:
[]' Analysis
,O Test O Ccinbination
' Identify PUMP tests pdrformed:.
O Shell hydro' static b.
O Bearing tem::erature a.
,.(ASME.Section III) evaluations OSeismiclo!iding d.
O Vibration levels c.-
C'Exploratoryvibrationf.
O Seal leakage 9 hydro press e.
~
(Fundamental frec.
)
g.
O Aging: O Thermal h.
O Flow per#cr=ance O Mechanical Are curves provided O Yes O No
'i.
O Pipe reacticn end O Others loads (ne::le loads-)
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~
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O Extreme envircnment:
O Humidity O Chemica' O Radiation 8.
Valve operability has been de:nonstrated by:
[] Analysis O Test O Cembination Identify VALVE tests performed:
a.
O Shell hydrostatic
' b.
O Cold cyclic List times:
Open Closee c.
[] Seismic loading d.
[] Het cyclic List times:
Open Ciesec e.
O Expieratory vibratien f.
O Main seat leakage (Fundamental frec.
)
I l
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7 g.
[} Aging: '[] ' Thermal h.
[]B'ackseatleakage
[] Mechanical 1.
[]Pipereactionend J.
[]Dischydrostatic loading k.
[]'Extremeenvironment 1.
[]Flowinterruptioncapability
[3 Humidity
[] Chemical
[] Radiation.
[]F1'owcharacteristics n.
[]Others m.
~
Are curves provided?
[]Yes []No 9.
As a result of any of the tests (or analysis), were any
' deviations frem design recuirements identified? []Yes []No If "Yes", briefly describe any changes made in tests (or analysis) or to the component to correct the deviation.
- 10. Was the test ec=ponent precisely identical (as to model, size, etc.) to the in-plant co=ponent? []Yes []No If "No", is installedccmpenent[]oversizedor[] undersized?
11.
If tvoe test was used to cualify the ccmponent, does the type tes: cest the retuirements of IEEE 323-1974, Section 5.?
[] Yes. [] No 12.
Is component orientation sensitive? []Yes []No []Unkncwn If "Yas", does installed orientation coincide with test crientation? []Yes []No 13.
Is the ccm onent mounted in the same manner in-plant as'it was curing testing (i.e., welded, same nuccer and size bolts, etc.)
[]Yes []ho [] Unknown
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- 14. Were the qualification tests perfomed in secuence and on only,-
one component?
[]Yes
[]No If "Yes" identify sequence (e.g., radiation, seismic, cyclic, themal, etc.):
15.
I'f " aging"4 was performed, identify the significant aging mechanisms:
. ~
- 16. ~ Identify loads imposed (assumed) on the component for the cualification tests (analysis) performed:
a.
[] Pl~ ants (shutdown loads) b.
[]Extremeenvironment c.
[]Seismicload d.
[]Others 17.
Have ecmponent design specifications been reviewed in-hcuse to assure they envelope all expected operating, transient, and
' accident tenditions? []Yes [] No 12.
Oces the ecmpenent utilize any unicue or special materials?
(Examples are special gaskets or packing, limitations on nonferrous materials, or special ccatings or surfaces.)
[]Yes.[]No If "Yes", identify:
19.
Does component recuire any special maintenance precedures or
~
practices, (including shorter periods between maintenance).
[] Yes []No If "Yes", identify:
20.
Is the qualified life for the compenent less than 40 years?
[]Yes [] No If "Yes", what is the cualified life?
As outlined in Section 4.4.1 cf IEEE-627 19EO.
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a SOUTH TEXAS PROJECT, UNITS l'AND 2 1
RE0 VEST FOR ADDITIONAL INFORMATION
GL83-5, ITEMS 4.1,4.2.1AND4.2.2
~
l INTRODUCTION Houston Lighting & Power Company, the applicant for South Texas Project, Units 1 and 2, submitted their response to Generic Letter 83-28 on November 3, 1983. The response has been reviewed with respect to Items 4.1, 4.2.1 and 4.2.2 of the Generic Letter. The applicant's response does not permit an evaluation of the adequacy of the periodic maintenance and trending programs for the breakers. The following information is required to evaluate compliance with Items 4.1, 4.2.1 and 4.2.2.
I.
Item 4.1 - Reactor Trip System Reliability (Vendor-Related Modifications).
The applicant stated that he will respond to this Item by January 1985. The NRC has not received this' response as of April 1985. The applicant i. 't'o s,ubmit to the NRC either:
1.
A statement confirming that all vendor-recommended 05-416 modifications have been or will be implemented; or 2.
A written evaluation of the technical reasons for any vendor recommended modification not implemented.
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II.
Item 4.2.1 - Periodic Maintenance Program for Reactor Tr~ip Breakers.
n'
~~ -
II.1 CriteriaforEvaluatingCompliancewithItem4.2.1 The South Texas Project, Units 1 and 2, Reactor Trip Systems utilize Westinghouse D5-416 circuit breakers.
The primary criteria for an acceptable maintenance program for the 05-416 Reactor Trip Breaker (RTB) are contained in Westinghouse Maintenance Manual for the DS-416 Reactor Trio Circuit Breaker, Revision 0, October 1984. The NRC staff, Equipment Qualification Branch, has reviewed this document and endorsed the maintenance program described in it.
More specifically,
, the criteria used to evaluate compliance include those items in this document that relate to the safety function of the breaker, supplemented by those measures that must be taken to accumulate data for trending.
II.2 Issues Relating to Item 4.2.1
~ = = "
.The applicant response' states that he will respond to Item 4.2 by June 1985.
South Texas Project, Units 1 and 2, periodic maintenance program for the reactor trip breakers should include, on a six-month basis (or when 500 breaker operations have been counted, whichever comes first):
j 1.
General inspection to include checking of breaker's cleanliness, f
all bolts and nuts, pole bases, arc chutes, insulating link, wiring and auxiliary swit'ches; 2.
The retaining rings inspection, including those on the undervoltage trip attachment (UVTA) and shunt trip attachment (STA);
2
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~
3.
Arcing and main contacts inspection as specified by the ;
~
-Westinghouse Maintenance Manual; 4.
UVTA check as specified'by the Westinghouse Maintenance Manual,
~
including replacement of UVTA if d'repout voltage is greater than
- 60*4 or less than 30'4 of rated UVTA coil voltage; 5.
STA check as specified by the Westinghouse Maintenance Manual; 6.
Lubrication as specified by the Westinghouse Maintenance Manual; 7.
Functional check of the breaker's operation prior to returning it to service.
South Texas Project, Units 1 and 2, Periodic Maintenance Program for the' reactor trip breakers should include, on a refueling interval basis (or when-500 breaker operations have been counted, whichever comes first):
1.
Pre-cleaning insulation resistance measurement and recording;
.w 2.
RTB dusting and cleaning; 3.
Post-cleaning insulation resistance measurement and recording, as specified by the Westinghouse Maintenance Manual; 4.
' Inspection of main and secondary disconnecting contacts, bolt tightness, secondary wiring, mechanical parts, cell switches, instruments, relays and other panel mounted devices; 5 '.
UVTA trip force and breake-load check as specified bv the Westinghouse Ma'intenance Manual;
- 6.
Measurement and recording RTB response time for'the undervoltage trip; l
7.
Functional test of the breaker prior to returning to service as specified by the Westinghouse Maintenance Manual.
3
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The maintenance procedure should include a caution to the maintenance personnel against. undocumented adjustments or mddif.i. cations to.RTBs.
The applicant is to confirm that the periodic maintenance program will
~
include these fourteen. items at the spfeified intervals or commit to their inclusion.
III. Item 4.2.2 - Trending of Reactor Trip Breaker Parameters to Forecast Degradation of Operability.
III.1 Criteria for Evaluating Compliance with Item 4.2.2 Four parameters have been identified as trendable and are included in the criteria for evaluation. These are (a) undervoltage trip attachment dropout voltage, (b) trip force, (c) breaker response time for undervoltage trip,_and (d) breaker insulation resistance.
III.2 Issues Relating to Item 4.2.2
-=="
The applicant is-to commit to inclusion of trip force, breaker respon'se time'andl dropout voltage for undervoltage trip and breaker insulation resistance as trending parameters. The applicant should also identify the organization which will perform trend analysis, how often the analysis will be performed, and now the information derived from the analysis will be used to affect periodic maintenance.
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