ML17054A282
| ML17054A282 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/06/1983 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Rhode G NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 8312190442 | |
| Download: ML17054A282 (60) | |
Text
Docket No'. 50-410 Mr. Gerald K. Rhode Senior Vice President Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202
Dear Mr. Rhode:
Subject:
Revised SgRT and PVORT Additional Information STR I8 UT.ION.:
~Document Control NRC PDR L PDR NSIC PRC LBII2 Rdg.
EHylton MFHaughey BBordenick, OELD ACRS
(.16)
- JMTaylor, DRP:IE Region I, RA DReiff Forms for SRP 3.10 and Request for Concerning Deep Draft Pumps OEQ 6 1983 Enclosure 10 of our March 29, 1983 letter on the Acceptance Review of the Application for an Operating License for Nine Mile Point Nuclear Station, Unit 2 included information pertaining to the Seismic gualification Review Team (SgRT) and Pump and Valve Operability Review Team (PVORT), which are part of the Equipment gualification Branch Audit Review Teams for SRP Section 3.10.
That enclosure has been revised and is included as Enclosure 1 to this letter for your information.
These revised forms should be used in subsequent work on this issue.
In addition, Enclosure 2 contains an Alternate Procedure for Detecting Problems with Deep Draft Pumps.
Your response to the request for information 271.10 indicated three residual heat removal
- pumps, one low pressure core spray pump and one high pressure core spray pump are deep draft pumps.
Provide a description on methods used at Nine Mile Point 2 to qualify long term operability of these deep draft pumps.
A schedule for submitting this information should be provided within two weeks of receipt of this letter.
If you have any questions concerning the request for additional information or attached information, please call the Licensing Project Manager, Mary F. Haughey at (301) 492-7897.
Sincerely, Qriginal si~<d b>
Enclosures:
As stated A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing cc w/enclosures:
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~ DL:LB82/BC MHaughey:kw ASchwencer lg/~83, 12/ P/83 83i2i90442 83i206 PDR ADQCK 050004i0
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Nine Mile Point 2
Mr. Gerald K. Rhode Senior Yice President Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 CC:
Mr. Troy B. Conner, Jr.,
Esq.
Conner 8 Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.W.
Washington, D. C.
20006 Mr. Richard Goldsmith Syracuse University College of Law I. White Hall Campus
- Syracuse, New York 13210 Mr. Jay Dunkleberger, Director Technological Development Programs New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.
Box 126
- Lycoming, New York 13093 Mr. John W. Keib, Esq.
Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202
0
e
'9~
Equipment gualification Branch Audit Review Teams Request for In'formation closure 1--
To confirm th 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 conduci a plant site audit and.review.
It is our intent to conduct a plant specific on-site Pump and Valve Operability Review Team (PVORT) audit
~and." a Seismic gualigication Reyiewi Team-:(SORT) audit; 1
f3 f
Il Since the site audit is performed on a sampling basis it is necessary to ensure that 85 to 90 percent of the safety related equipment are qualified and installed before the audit.
In order that the staff is familiar with the seismic and dynamic qualification programs currently being conducted, it is re uested that all test ro rams be identified b
submittin a brief descri tion of the ro ram, items bein
- tested, the vendor or the testin laborator
- involved, and the dates and location of the tests.
Information about the ongoing test programs should be submitted as soon as possible so that the NRC staff can review and witness relevant tests for selected items.
A list of all safety-related equipment should be provided so that an assessment of the equi pment qualification status can be made by the staff.
. Equipment should be divided first by system then by component type.
Attach-ment
~l shows a tabular format which should be followed to present the status summary of all safety-related equipment.
w - -aei
V After the information on Attachment 81 is received, and it is determined that the equipment qualification is substantially
- complete, selections will be made of the equipment to be audited, and reviewed, by the SgRT and PVORT.
Specific information on equipment selected for audit by each
.revi ew team will be requested.
The information that will be requested for those equipment selected by the S(RT is shown in Attachment 82.
The information that will be requested for those equipment selected by PVORT is shown in Attachment b3.
In addition, the applicant will be requested to provide a complete set of floor response spectra identifying their applicability to the equipment listed in Attachment 81.
For the equipment selected by the SgRT for audit, the combined Required
Response
Spectra (RRS) or the combined dynamic response will be reviewed.
The SgRT will examine and compare 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 standards and agrees with the RRS.
In cases where the plant is a
BHR facility, the equipment qualifying documentation must also provide evidence that the hydrodynamic loads in the (0 - 100)
Hz frequency range have been accounted for.
a For the equipment selected by the PVORT for audit, the applicant must provide evidence that appropriate manufacturers.'ests
.have been conducted;
- reviewed, and approved, and that the equipment meets, or exceeds the design requirements.
The applicant must also provide qualification test an'd or analysis results that provide assurance that the equipment will operate (function) during and following the Design Basis Events (DBE) and all appropriate combinations thereof.
The specific information requested in,Attachments.82, and P3 should be provided to the NRC staff two weeks prior to the plant site visit.
The applicant should make available at 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 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 e ui ment im ortant to safet 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 3.10 of the Standard Review Plan Revision 2
(NUREG-~+00).
Another element of the seismic and dynamic qualification review deals with the containment isolation valves for the purge and vent systems to assure their ability to close against postulated accident pressure inside contain-ment.
Information needed for this review and the basis for the review are provided in Attachments 4 and 5.
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ATTAC)<ViEHT gl B MASTER LISTING OF SEISMIC AND DYHAIAIC QUALIFICATIOH SUMMiARY AHD STATUS OF SAFETY-REL'ATED EQUIPMENT e ASSOC IA ED EXPLANATORY NOTE
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H/STER Ll&TIMG OF SEISIN(C Wo AWAMIC QuhilFICATIOH SWIM'YWDSr87IJS<< ~~~~~
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'-:'LAtf1 IQhfE:
yp gKEq g 0-(JTl LtYY:
p/E:
I ITS I rA6 F-FOR.
EQU(PM Ebl T L I S TED BELOW'/
I~>E SVPPIIFR IS-HIE'3, ASST ~, OTHER +.
SAFHSYSTEM k'UNCT!ON PRE:.
t>EAT.
vo E@ul f M CRT vl=-sT RAtP QU/N NO.
~y P I=
gN D M~tJU~CTUQ'ND DM'C QI PT /0 N halo>Eg.
NO.
L aA,~S
+VALIFI4hylo 0
CONS IDF RED Mg7IIaa
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f+S noN GoILOIN6 goNg SgJS. 0nle'4a gggL AHD'yIIPIPlPW gLBYATIo+TI~I~ M AII~ (ZPh) YSIS LOWP5T II'INi pp<Fd( 0EAIC'f 57ATUS F/8 6 S OIz) v o,vAL fNsl-fFlg ABA-
)f8)
TION TloN RRS CODES Ag~
Swag>A RDS
d A
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(2)
I A
HCH'EHT A'I (Continued)
NOTES TO MASTER LISTING The information on Pl'ant
- Name, Do"ket Ho., etc.,
are pertinent to the power station and will be the sa~e for all sheets.
The equipment is listed by supplier (circle one after "SUPPLIED BY:") and by system (indicate name and function of syste~ after "SYSTEM AHD 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 Pemoval, Containment Fission Product
- Removal, Containment Combustible Gas Control, Auxiliary Feedwater, Containment Ventilation, Containment Radiation Monitoring, Control Room Habitability System, Ientilation for Areas Containing Safety Equipment, Component Cooling, Service
- Vater, Emergency Systems to Achieve Safe
- Shutdown, Pos accident Sampling and Monitoring, Radiation Monitoring, Safety-Related Display Instrumentation.
The supplier will usually he either A/E or NSSS.
Use separate sheets for each system.
Use additional sheets when a given system has more equipment than can be listed on one sheet.
(3)
"IDENT. NO." is to be filled in by the organization preparing the list.
Each equipment listed should have separate identification number.
The following form is reccmmended:
(a)
For A/E supplied equipment, the number may be "BOP-XXX." If more than'one group is preparing forms, the number may be "BOP-M-XXX" (Mechanical) or "BOP-IC-XXX" (Instrumentation and Control).
(b)
For NSSS supplied equipment, the. number may be NSSS-M-XXX, HSSS-IC-XXX, etc.
<<)
(c)
The number written on each line (for each listed equipment) should be an ordered numeric listing for the above indicated-XXX (-001 through ccmpletion).
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 parenthesis should be the "BOP-M," "HSSS-IC, " etc.
The "TYPE" refers to its generic
- name, such as pressure transmitter, indicator, solenoid value, cabinet, etc.
Equipment type should be described by indicating for example, motor driven pump, turbine driven pump, motor operated valve, air operated
- valve, 18" valve, etc.
Following abbreviations can be used where appropriate.
Val ves:
BV - Ball valve, BFV - Butterfly valve, CV - check valve, DV - Diaphragm valve, GV - Gato valve, GLV - Glove valve, SV -. Safety Valve, RV - Relief Valve Pumps:
CP - Centrifugal
- pump, PDP -'ositive displacement
- pump, DDP - Deep draft pump,
'JP - Jet pump.
~ )
guantity refers to the number 'of the same" equipment vsed in the pl ant.
Under mounting condition indicate the fol )owing as applicable:
CF for C4'or DH for HH for RH for CY) for EN for concrete floor mounting concrete wall mounting di rect mounting hanger mounting rack mounting.
cabinet mounting equipment mounting tlounting details such as number of bolts, weld leng.h, etc.
need not be indicated here.
(s)
(IO)
The columns "SEISNIC" and "OTHER DYNAMIC" need only be checked (X) if applicable.
In the case of BWRs indicate "H" under "OTHER DYHANIC" column where qvalification includes hydrodynamic loads.
Under "RE/'0 INPUT (ZPA)," the applicable "g" level should be p'rov id ed.
Under gualification Method under analysis, indicate "S" for static, and "D" for dynamic; under test frequency, indicate "SF" for single, and "NF" for multiple; and vnder text direction, indicate "SD" for
- single, "MD" for multiple.
Equipment status is to be addressed separately to qualification and to instal 1 ati on.)
The applicable letter shovld be provided vnder the column headed "EQUAL," according to the following code:
A The qualification and associated documentation are ccnplete.
The qvalification testing is finished but associated documentation is not yet submitted or still in review.
)
The qualification plan/procedure is documented, but testing has not yet begun.
D Equipment to be qualified.
E Equipment is judged not qualifiable and will be replaced with qualified equipment.
F For BAR plants only:
Equipment is qualified for, seismic loading only.
Requalification will be performed to account for the suppression pool hydrodynamic loading effects.
The applicable letter should be provided under the column headed "INSTALLATION,"according to the following code:
A Installation is ccepleted.
Equipment
'.s ready for service.
8 Eqvipment mounting/hookup is ccrnpleted, but significant parts of the eqvipment are not yet installed.
C Equipment is located at its intended service location, but mounting and/or hookup is not conpleted.
D The equipment is not installed and is not available for i nspecti on.
(11) The Required
Response
Spectra (RRS) package should be provided along with the toaster Listing.
Only response spectra applicable to the listed equipment shovld be included, each numbered for reference under the column headed "RRS REF. "
In many cases, several equipment will reference the same RRS.
'(12)
Codes and Standards A'pplicable codes, standards and Regulatory Guides should be indicated here, for example, ASNE Section III Class 2; IEEE-344, 1975, 323-1974, 382-1972; ANSI N278-1., Regulatory Gvide 1.100, 1.148 etc.
Seismic and D namic ualification Summa Attachment f2 of E ui ment
+~+ g~C~
I.
Plant Name:
l.'t'.lity:
PMR:
2.
NSSS:
3.
A/E:
BMR:
Other II.
Component Name:
1.
Scope:
I
] NSSS 2.
Model Number:
3.
Size or Range:
4.
Yendor:
3 BOP j Other guantity:
- 5. If the component is a cabinet or panel, name and model Number of the devices included:
6.
Physical
==
Description:==
a.
Appearance:
b.
Dimensions:
c.
Meight:
7.
Location:
Building:
Elevation:
8.
Field Mounting Conditions
] Bolt (Ho
, Size
)
j 9.
l1ounting Orientation t,e.g.,
on floor, cantilevered, suspended, etc.j 10.
a.
System in which located:
b.
Functional
==
Description:==
c.
Is the equipment required for L
j Hot Standby [
J Cold Shutdown j Both
[
j Neither L
j Other
0
ll.
Pertinent Reference )Design Specifications 'for /vali+'cation Requirements:
a.
Seismic Input b.
Hydrodynamic Load Input c.
Fatigue Considerations d.
Service Conditions e.
qualified Life'II.
Is E ui ment Available for Inspection in the Plant:
[
3 Yes
[
No
]
Partial or limited availability IY.
E ui ment Oualification Method:
] Test
] Analys i s equal ification Report*:
(No., Title and Date):
Company that Prepared Report:
Company that Reviewed Report:
f 3 Combination of Test and Analysis Mhere Report is filed or available:
Applicable Codes And/Or 'Standards:
V.
Vibration In ut:
1.
Loads considered:
a.
[ ] Seismic only b.
[ l Hydrodynamic only c.
[ ] Vibration from normal operation j Combination of ('a), (b), and (c) 2.
Hethod of Combining RRS:
[
] Absolute Sum
[
3 SRSS
~other, specify) 3.
Required
Response
Spectra"* (attach the graphs):
NOTE:
- Ifmore than one report complete items IV thru VII for each report.
- Ifother than RRS is used, describe method.
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4.. Damping Corresponding to RRS:
OBE S
SSE 5.
Required Acceleration in Each Direct:
[
] ZPA
[
] Other speci fy OBE S/S
=
SSE S/S
=
F/B
=
6.
Were fatigue effects considered:
[
]Yes
[
]No If yes, describe how they were treated in overall qualification program:
VI.
If ual ification b
- Test, then Compl ete:
l.
[
] Single Frequency
[
] Hulti-Frequency random sine beat 2.
[
] Single Axis
[
] Independent Axis
[
] Hulti-Frequency
[
] In-phase motions 3.
Numbe, of gualifications Tests:
OBE 4.
Frequency Range:
SSE Other speci fy 5.
Natural Frequencies in Each Direction (Side/Side, Front/Back, Vertical):
S/S
=
F/B 6.
Hethod of Determining Natural Frequencies
[
] Lab Test
[
] In-Situ Test
[
] Analysis 7.
TRS enveloping RRS using Hulti-Frequency Test
[
Yes (Attach TRS
& RRS graphs)
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[
]No
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8:
Maximum Input g Level Test:.
OBE S/S
=
OBE S/S
=
9.
Laboratory Mounting:
F/B
=,
F/B
=
V =
A.
[
] Bolt (No.
, Size
)
[
] Weld (Length
)
[
]
B.
Orientation and Fixturing:
'10.
Functional operability verified:
[
] Yest
[
] No
[
] Not Applicabl ll.
Test Results including modifications made:
12.
Other tests performed (such as aging or fragility test, including results):
13.
Failure Modes. (If appropriate 14.
Margins Available:
[
] Input Spectrum
[
] Fragility VII. If qualification by Analysis, then complete:
1.
Method of Analysis:
[ ] Static Analysis
[
] Equivalent Static Analysis
[
] Dynamic Analysis:
[
] Time-History
[
] Response Spectrum Natural Frequencies in Each Direction '(Sid'e/Side, Front/Back, Vertical):
S/S '=
F/B
=
3.
Model Type:
[
] 3D
[
] 20
[
] 1D
[
] Finite Element
] Beam
[
] Closed Form Solution
[
] Other
I
,4 5.
L 3 Computer Codes Frequency Range and No. of modes
[ ] Hand Calculations Method of Combining Dynamic Responses rom Seismic and Other
, Dynamic Loads:
] Absolute Sum 3
SRSS
[
3 Other:
specify) 6.
Damping:
OBE SSE Basis for the damping used:
'I 7.
Support Considerations in the model:
8.
Critical Structural Elements:
Governing Load or Response Seismic A.
Identification Location Combination Stress Total Stress Stress Allowable B.
Maximum Critical Deflection Location Maximum Allowable Deflection to Assure Functional 0 erabilitv 9.
Failure Modes:
10.
Margins Available:
[ ] Input Spectrum
[
] Stress or Deflection e
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EQUIPMENT QUALIF ICATION BRANCH PUMP AND VALVE OPERABILITY REVIEW TEAM REQUEST FOR ADDITIONAL INFORMATION In'ight of increased emphasis on mechanical equipment qualification, the Pump and Valve Operability Review Team (PVORT) has been formed to review the pump and valve operability assurance program for those utilities applying for their operating license.
The PVORT will review these programs by selecting various pumps and valves that are important to safety and then verifying that these components are qualified to perform their necessary functions when subjected to those loads, associated with normal, upset, emergency, and faulted plant conditions.
The findings of the team's review will 'then be included in'%he"staff z'safety evaluation report (SER)..he basic criteria used by the PVORT to determine the acceptability of
'the applicant's pump and valve operability assurance program are stated in SRP 3.9.3.
Two other documents are also used for basic guidance:
1 SRP 3.10, and IEEE-627.. Spec'ific references are provided within the flrst two documents; All of these references, as well as good engineering judgement, will aid the PVORT in making recommendations concerning the adequacy of the applicant's pump and valve operability assurance program.
To aid the PVORT in this review, the. staff requires that a
"Pump and Valve Operability Assurance Review" form be prepared by the applicant for each selected component and submitted to the staff two weeks prior-to the team's plant-site visit.
The applicant should also make available for review all pertinent documents and reports conce'ming the qualification of the selected components.
Specifically, the documentation package for each of the selected components should include documents that will provide the type of information listed in SRP 3. 10, page 3.10-9, a-l, as well as purchase specifications and plant test pr ocedures,
( applicable sections).
The PYORT is particularly interested in insuring that sequential testing and failure mode determination (aging) are addressed; and that analyses are supported by test documents, whenever possible..Another topic of discussion during the audit will be the applicant's maintenance/surveilance
0 0
. orogram and how that program interfaces with the applicant's operability assurance program.
It should be noted that it is beyond the charter of the PVORT to make assessments involving the applicant's overall seismic and environmental qualification programs even though seismic and environmental qualification are addressed and included in the pump and valve operability assurance program.
REFERENCES 2.
U.S. Nuclear Regulatory Commission Standard Review Plan, Section 3.9.3, NUREG-75/087.
U.S. Nuclear Regulator~.Comnission Standard Review 3'lan,'ection 3.10, NUREG-0800 (Formerly NUREG-75/087).
3.
t IEEE Standard for Design gualification of Safety Systems Equipment Used in Nuclear Power Generating
- Stations, IEEE Std. 627-1980.
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PUYiP AND VALYE OPERABILITY ASSURANCE REVIEW I.
PLANT INFORMATION Name:
3.'tility:
4.
NSSS:
5.
A/E:
Unit No..
2.
Docket No.:
C.P.
Docket Date:
C.P.
SER Date:
I/ I
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GENERAL COMPONENT* INFORMATION l.
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'.2.
Location:
a.
Building/Room b-Elevation c.
System
~ spmy'.
4 ~
5.
Component I.D. No. on PEID dwg:
1 If component is a [] Pump complete II.5; If component is a [j Valve complete II.6.
Gerieral Pump Data Name Mfg.
Model S/N Type a.
Pump b.
Prime-mover Name Mfg.
Model S/N Type The component, whether pump or valve, is considered to be an assembly composed of the body, internals, prime-mover (or actuator) and unc sonal accessories.
I
a.
Pump (conti Q9)
Overall Dimensions Weight Mounting Method prime-mover (tinued)
Overall Dimensions Weight Mounting Method Required B.H.P.
H.P.
Prime-mover requirements:
Component System System
( include normal, maximum Parameters:
~Desi n
Normal Accident and minimum).
Press Temp Motor (voltage)
Flow He ad - -- --- -- -. ---- "
"-Media-l Required NPSH at maximum flow Available NPSH.
v Turbine (pressure)
If MOTOR l.ist:
Duty cycle Operating Speed Critical Speed Stall current Class of insulation List functional accessories:*
Functional accessories are those additional sub-components that are required to make the pump assembly operational,.(e.g.,
- coupling, lubricating oil system, speed control system, feedback, etc.)
Include manufacturer and model number.
6.
General Valve Datl a.
Val.ve b.
Actuator (if not an integral unit)
Name Mfg.
Model Name Mfg.
Model S/N Type Size S/N Type.
Size Weight Weight
~
~
Mounting
- Method.-..
Mounting...
'ethod
" a '. a M>>' ~ m m4~:
w-a4'-
~ yS., a
<Required Operating Torque Maximum Delivered Torque Component System System Parameters:
~Desi n-Normal Accident Press
.,Power requirements:..
'-.:-(include normal,. maximum
.and minimum).
E 1ectri cal
. Temp Flow Media Max aP across valve Pneumatic/Hydrau1 ic Closing time 9 max hP Opening time 8 max aP l.ist functional accessories:*
I 8
1.
Describe components normal and safety functions (include accident initiating signals, if applicable):
Normal:
c I(
~ h% ~ t
~
l Safety:.
~ NW
~
.2.
-The -components normal state is:
- '- [j Operatin'g",
[] Standby 3.
Safety function:
I a.
[] Emergency reactor shutdown b.
[j Containment heat removal c.
fj Containment isolation e.
[j Reactor core cooling d.
--Ej
[j Reactor.
heat removal Prevent significant'eleaseof radio-'
active material to environment g.
[j Does the component function to mitigate the consequences of one or more of the fol.lowing events?
[j Yes [j No If "Yes", identify.
[j LOCA
[j HELB
[j Other
[j.MSLB Functional accessories are those additional sub-components that are required to make the valve assembly operational,.(e.g., limit switches, solenoid valves,. accumulators, etc.)
Include manufacturer and model number..
J
4.
Safety 'equiremen
[j Intermittent Operation
[j During postulated event fj Continuous Operation
[j Following postulated event If component operation is required following an event, give approximate length of time component must remain operational.
(e.g.,
- hours, days, etc.)
t
- IY.
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QUALIFICATION.
I 1.
Reference by specific number the design codes and standards used as a guide to qualify the component:
~ +as,
~
~
9
=
~
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5.
For YALVES:
Does the component
[j Fail open [] Fail closed
[j Fail as is Is this the fail safe position?
[j Yes
'[j No Is the valve used for throttling purposes?
[] Yes.[j No.
What is the maximum acceptable internal and external leakrate?
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2.
Have acceptance criterias been established and documented in the test plan(s) for the component?
[j Yes
[j No
'3.
Are the margins* identified in the qualification documentation?
[j Yes.
[j No 4.
Was the component that was qualified a model or an actual assembly?
If a model, what was its scale?
If an actual assembly,'as it qualifie as an assemo or y sub-assemblie
?
(i.e., valve,
- actuator, pump, river Yiargin is the difference between design basis parameters and the test parameters used for equipment qualification.
/)
5.
List all compon'en sts performed or to be perfo that demonstrate qualifscatson:
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'0 g
~
6.
List all component analyses performed that demonstr'ate qual ification:
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7.
As a result of any of the tests (or analysis),
were any deviations from design requirements identified? [] Yes [j No If "Yes",.briefly describe any changes made in tests (or analysis) or to the component to correct the deviation.
0
t Cp
Q Was the tested corn onent precisely identical (as o model, size, etc.) to the in-plant component?
[3 Yes [j No If "No", is installed component [j oversized or [] undersized?
Is component orientation sensitive?
[j Yes [j No [j Unknown If "Yes", does installed orientation coincide with test/analysis orientation?
[j Yes [j No 10.
List all plant loading conditions considered during tests or
=-
analysis; (e.g.,
normal, upset, emergency, faulted).
11.
What is the fundamental frequency of the component?
12.
Does the component have a unique design or utilize unique material in its construction'?
(Examples are special gaskets or
- packing, one of a kind components, limitations on nonferrous materials, special coatings or surfaces, etc.)
[ jYes
[ jNo If "Yes" identify:
13.
What is the design (qualified) life of the component, exclusive of normal maintenance items such as packing, bearings,
- seals, diaphragm,
- gaskets, and other elastomers?
14.
Which of the components normal maintenance items requires the most frequent replacement/repair?
What is the normal time interval between replacements/repairs?
15.
List the harshest environmental conditions that the component could be exposed to during or following an accident, [e.g.,
temp.,
- pressure, humidity, submergence, radiation (type and dose), etc.j:
t'
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Information Concerning qualification Documents for the Component Report Number Report Titie Date Company Organizat on Pre arin Re ort Company/Or g an > zat i on Reviewin Re ort I00 I
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S A
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Enclosure 2
LONG TERM OPERABILITY OF DEEP DRAFT PUMP In July 1979, IE issued Bulletin 79-15 which focused on the problem of long-operability of deep draft pumps.
A set of guidelines were developed to aid the review of this issue, and were sent to all licensees and applicants.
These guidelines described one method of showing operability which involves running the pump for periods of 6, 48, and 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and disassembling the pump 3 times to check the bearing wear.
Our experience to date is that this method has been regarded as excessive and unnecessary.
An alternate qualifi-cation method which incorporates vibration monitoring and some standard plant test procedures is attached.
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Alterna te rocedv re for Detect i no P robl ems Mith Dee Draft Pumps Concerns identified for these pumps include:
1.
Stiffness of the rotor and casing structure.
2.
Natural vibration freqvencies occurring near the pump operating speed.
3, Vortices at the pump inlet imposing random and periodic loads.
4.
Nisalignment,,between pump shaft and motor column.
Mater Quality The existence of these problems irt an individual pump should become evident throvgh a combination of a properly'erformed seismic and deflection analysis and a carefvlly planned testing and sur veillance procedure.
Following dis-cussions indicate examples of the important elements and the depth and details of such a procedure.
Good pump assembly alignment procedures should-be practiced when assembling I
the pump followed by hand ~turnin the pump to assure there is no bindinp'r major misalignments.
After assembling the following vibration monitoring should be performed:
Prior to full power opera.ion of the plant each deep draft pump should have experienced a minimum of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of operation under full system temperature and pressure.
Full system temperature should simulate the
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system parame.ers, under most challenging design conditions, which'est represent the conditions during which the pump will be expected to perform its function.
'(lithic the first 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of operation in the plant at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will be continuous operation during which vibration levels will be measured every 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
(+ 30 min.).
Readings should be taken during stable operating conditions. 'll readings taken shall be recorded.
Anomalies in vibration levels should be explained.
Following the, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> continuous running period, and on about the 00th hour and 100th hour of plant pump running time, vibration measurements are to be repeated.
These readings should be-taken duri ng a period of stable running conditions as near to the 50 hour5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> and 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> running time as 'possible but at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> apart.
The pump shall be operated for a sufficient period prior to full power operation to facilitate the measurements prescribed above.
Ãnile aeasvring vi$ration at the times prescribed above, the-following p
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kib readingare to be performed per the method described in Section XI para-graph.IMP-4500 of the ASME B&PY Code, wtth exceptions as previously noted.
"Reference" and "Required Action" vibration levels should be established during this portion of the testing.
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~ 1 Vibration measurements are to be compared to the acceptable vibration range specified by the vendor.
A threshold vibration level should be establ'ished from an acceptable vibration level with due considera-r tion of sufficient margin to assure that the pump can still perform its safety function when this threshold vibration level is reached; and should be maintained as the lower'bound "required action" value for the performance of inservice vibration testing.
In addition, each of the readings are to be compared for signs of degradation in the pump bearings or for the radial vibration amplitude changes.
2.
Qn a schedule concurrent with in-service test, as a minimum, vibration levels shall be measured for these pumps.
Prior to performing these h
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temperature variation of 3% or less}.
These measurements are to be performed in the same manner as in item'1 and the same parameters are 1
to be recorded.
Results are to be compared to those recorded in item 1
for signs of degradation or radial changes.
Yalues are to be plotted and extrapolated to predict pump bearing life.
If vibration levels measured during this period show signs of degra-,
dation or reduced bearing life the cause should be determined and corrective action taken as appropriate (i.e., whenever the threshold or "Required Action" values are exceeded.)
Following corrective action, vibration levels shall be measured to determine adequacy of corrective action.
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3.
Following pump disassembly and reassembly the pump must be hand turned to assure that there is no major misalignment.
Vibration measurements shall then be performed as described in item 2 either prior to return to operation or within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of returning to operation.
4.
The pump casing should be provided with lateral restraints to prevent, the pump impeller from experiencing undesirable lateral deflection while in rotary motion.
F Since the bearings are cooled by the water flowing through the pump, the quality of water should be such that there are no suspended particles to cause premature bearing failure.
Maximum particle size allowed in the water should be developed in consultation with the manufacturer.
For pumps with intermittent service the nature of dissolved solids should be controlled carefully so that deposit of solids on bearing surfaces does not cause premature bearing failure.
The concern about the quality of water with regard to long-term operability of deep draft pumps stems from its potential for becoming a
common cause of fa ilure.
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