ML17276B598
| ML17276B598 | |
| Person / Time | |
|---|---|
| Site: | Columbia |
| Issue date: | 08/09/1982 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Ferguson R WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| NUDOCS 8208240101 | |
| Download: ML17276B598 (24) | |
Text
r tssz Docket No. 50-397 Mr.,R. L. Ferguson Managing Director Washington Public Power Supply System P. 0. Box 968 3000 George Washington Way Richland, Washington 99352
..DISTR IB UTION:
C~2 NRC PDR L
PDR NSIC PRC LB¹ 2 Reading EHylton RAuluck OELD ISE ACRS (16)
Region V
Dear Mr. Ferguson:
Subject:
Request for Additional Information -
PVORT Audit Enclosure 1 describes the information required by the NRC staff prior to conducting the on-site Pump and Valve Operability Review Team (PYORT) audit, tentatively planned for September 1982.
After you provide the information called for in Attachment 1 of the enclosure and it is determined that equip-ment qualification is lessentially complete, the PVORT will then select indi-vidual ply'ces of equipment for audit and will noti.fy you of thy selection.
The information called for in Attachment 2 of the enclosure fof'he approx-imately ten to twelve selected pieces of equipment must then be provided to the NRC staff at least two week prior to the audit.
Since thi;s review is being conducted with the assistance of the national laboratories, we request that one copy of your responses by sent to:
Mr. J.
N. Singh EGINIG Idaho, Inc.
P. 0. Box 1625 Idaho Falls, Idaho 83415 Any questions regarding this request shall be'directed.,',to Dr. Ra(ender Auluck, (301) 492-9778, the Licensing Project Manager.
Sincerely,
Enclosures:
As stated cc:
See ext age A. Schwencer, Chief Licensing Branch No!.2 Division of Licensing 8 8 0 8 2 4 0 l0-'/ p OFFICEI SURNAME/
DATE Q R uluc
.kab 7/ g< /82 LB¹2:D
~ ~ ~ ~ ~ ~ ~ ~ ~
AS hw cet
/82 NRC FORM 318 (10-80j NRCM 0240 OFF ICIAL R ECOR D COPY USGPO: 1981-339 960
~ I
WNP-2 Mr. R. L. Ferguson Managing Director Washington Public Power Supply System P. 0. Box 968 3000 George Washington Way
- Richland, Washington 99352 cc:
Nicholas Reynolds, Esquire Debevoise 5 Liberman 1200 Seventeenth
- Street, N.
W.
Washington, D. C.
20036 Mr. G.E.
Doupe, Esquire Washington Public Power Supply System P.O.
Box 968 3000 George Washington Way Richland,'ashington 99352
'icholas Lewis; Chairman Energy Facility Site Evaluation Council Mail Stop PY-11 Olympia, Washington 98504 Roger Nelson, Licensing Manager Washington Public, Power Supply System P.O.
Box 968 Richl and, Washington 99352 M0. W.G. Conn, Sr.
N/M Group Supervisor Burns and Roe, Incorporated
. 601 Williams Boulevard
- Richland, Washington 99352 Mr.. Richard Feil-U.S.
NRC Resident Inspector WPPSS-2 NPS
'P.O.
Box 69 Richl and, Washington 99352 Dr. G.D. Bouchey Dept Director, Safety 8 Security Washington Public Power Supply System P.O. B,ox'68, MD 650
- Richland, Washington 99352
Equipm%t qualification Branch Audit Review Teams Request for In'formation Enclosure 1
To confirm the extent to which safety-rela'ted equipment meets the requirements of the General Oesign Criteria (GDC) of 10 CFR Pari 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 Team (PVORT) audit concurrent with the Seismic gualification Review Team (SgRT) audit.
Me believe such scheduling should minimize manpower and scheduling conflicts for the applicant, the NRC staff, and our technical assistance contractors.
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'eismic 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 equipment qualification status can be made by the staff,.
Equipment should be divided first by system then by component type.
Attach-ment hl shows a tabular format which should be followed to present the status summary.of all, safety-related equipment.
5EsIGNATED-OBzQXÃkU CertU'1el By.
0
. After the information on Attachment 81 is;received, and it is determined "that the equipment qualification is substantial'ly 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 review team will be requested.
The information that will be requested P
for those equipment selected by PVORT is shown in Attachment h'2..
In addition, the applicant..will be requested to provide a compl.ete set of floor response spectra, identifying their applicability'o the equipment listed in Attachment gl.
For the equipment selected by the PVORT for audit, the applicant must provide evidence that appropriate manufacturers.',
tests have been conducted,
- reviewed, and approved, and that the equipment meets,. or exceeds the design requirements..
The applicant must also provide qualification.-test and or analysis results that provide assurance that the equipment wil,l, operate(function) during and following the Design Basis Events (DBE) and all appropriate combinations thereof.
The specific information requested in Attachment 82,: 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 shoul.d be removed for. all e ui ent.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 quali.fication is complete.
The acceptance criteria for-requirements on records is provided in Section 3.10 of the Standard Review Plan;Revision 2 (NUREG-800).
. ATTACHMENT PI I MASTER LISTING OF. SEISMIC AND DYNAHIC (}UALIFICATIQH
SUMMARY
AND STATUS OF SAFETY-RELATED E(UIPMENT' ASSOC IA ED EXPLANATORY NOTE
)t gggTEg I.i&7lgG OF S EISHIC P gg DyhlPP,NIC QOALIFICATIOH
SUMMARY
'AHOSTBTUSOF &,re T,Y.F T<> ~'MPNEC7i::
F LANT HAMeP
>acKe.V NO-.
u>iLI~Y:
Fdg.
EQUIPM EH 7 LlS TED BPL.ON/
"llE SUPPI.IFF'S
= PIE 0, NESS l3,'OT}ICR E3, SAFTY SVSTBf k'UNCTION hRF-:
DENY:
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NO.
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8 rAMDA
ATTACHMENT 11-(C ontinued )
NOTES TO MASTER LISTING (2)
The information on Plant
- Hame, Docket Ho., etc.,
are pertinent to the power station and will be the same for all sheets'.
The equipment is listed by supplier (circle one after "SUPPLIED BY:") 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, Steanline Isolation, Main Feedwater Shutdown and Isolation, Emergency
- Power, Emergency Core Cooling, Containment Heat
- Removal, Containment Fission Product
- Renoval, Containment Ccnbustible Gas Control, Auxiliary Feedwater, Containment Ventilation, Containment Radiation Monitoring, Control Roc'abitability System, Ventilation for Areas Containing Safety Equipment, Component Cooling, Service
- Vater, Emergency Systens to Achieve Safe
- Shutdown, Postaccident 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)
(a)
"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 recanmended:
~ (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,
'SSS-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 canpletion).
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," "NSSS-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 punp, motor operated valve, air operated
- valve, 18" valve, etc.
Following abbreviations can be used where appropriate.
Val ves,:
BV - Ball valve,
'GV -. Gato val ve, Pumps:
CP - Centrifugal JP -"Jet pump.
BFV - Butterfly valve, CV - check valve, DV - Diaphragm valve, GLV - Glove valve, SV - Safety Valve, RV - Relief Valve
\\
pump,'DP -'ositive displacement
- pump, DOP - Deep draft pump,
(s)
(6)
'gvantity refers to the number of the same equipment used in the pl ant.
Under mounting condition indicate the following as applicable:
CF for concrete floor mounting CH for concrete wall mounting DH for direct mounting HH for ha'nger mounting RH for rack mounting CM for cabinet mounting EH for eouipment mounting Hounting details such as number of bolts, weld length, etc.
need not be indicated here.
(7)
The columns "SEISMIC" and "OTHER DYNAHIC" need only be checked (X) if'applicable.
In the case of BWRs indicate "H" und'er "OTHER DYNAHIC" column where qualification includes hydrodynamic loads.
(8)
Under "RE/'0 INPUT (ZPA)," the applicable "g" level should be provided.
(g)
Under gualification Method and "D" for dynamic; under and "HF" for multiple; and
- single, "HD" for multiple.
under -anaTysis, indicate "S" for static,,
test frequency, indicate "SF" for'ingle, under text direction, indicate "SD" for' Equipment status is to be addressed separately to qualification and to instal 1 ati on.i The applicable letter should be provided under the-column headed "gUAt," according to the following code A
The 'qual ification and associated documentation are ccnplete.
he qualification testing is finished but associated documentation is not yet submitted or still in review.
I The qualification plan/procedure is'ocumented, but testing has not yet begun.
Equi pment to be qu al ified.
D E
Equipment is judged not qualifiable and will be replaced with
'u al ified equi pment.
F For BAR plants 'only:
Equipment is qualified for seismic loading only.
Requalification will be performed to account
'or the suppression pool hydrodynamic loading effects.
The applicable letter should be provided under the column headed "INSTALLATION,"according to the following code:
Installation is conpleted.
Equipment is ready for service.
Equipment mounting/hookup is ccmpleted, but significant parts of the equipment are not yet installed.
C Equipment is located at its intended service location, but mounting and/or hookup is not ccmpleted.
D The equipment is not installed and is not available for i ns pecti on.
(ll) The Required
Response
Spectra (RRS) package should be provided along with the toaster Listing.
Only response spectra. applicable to the 1-isted equipment'hould be included, each numbered fo'r reference under the column headed "RRS REF.'"
In many cases, several equipment will reference the same RRS.
(l2) Codes and Standards Applicable codes, standards and Regulatory Guides should be indicated here, for example, ASME Section III C'ass 2; IEEE-344, 1975, 323-1974; 382-1972; ANSI N278-1, Regulatory Guide 1.100, 1.148 etc.
a Attachment 82 PUMP AND VALVE.
OPERABILITY ASSURANCE REVIEW I.
PLANT INFORMATION 1.
Name:
3.
Utility:
4.
NSSS:
5.
A/E':
Unit No.
2.
Docket No.:
L] PMR rj BNR II.
GENERAL COMPONENT* INFORMATION 1.
Supplier: [j NSSS
{ ] BOP 2.
Location:
a.
Building/Room
- b.
Elevation c.
System 3..
Component'umber on in-house drawings:
4.
If component is a f] Pump complete II.5.
If component is a I ] Valve complete II.6.
A 5.
General
~Pum Data r
Mfg.
Model S/N Type a,
'ump b.
Prime-mover Name i
Mfg.
Model S/N Type The component, whether pump or valve, is considered to be an ~assembl composed of the body, internals, prime-mover (or actuator) and functional accessories.
0 a.
Pump (continued)
~ <<Q Size Size Weight Mounting Method Required B.H.P.
Parameter
~Desi n
~0oeratin Press Weight Mounting Method H.P.
Power requirements:
(include
- normal, maximum and minimum).
Electrical Temp Flow Head Other Required NPSH at maximum flow Available NPSH
-Operating Speed If MOTOR list:
Duty cycle Stall current Class of insulation Critical Speed List functional accessories:*
List control signal inputs:
Functional accessories are those sub-components not supplied by the manufacturer that are required to make the pump assembly operational, (e.g., coupling, lubricating oil system, etc.)
'4 P
6.. General Valve Data,.
a.
Yalve
-=- '":-:.'.-....
b.
Actuator (if not an integral unit}
Name
- 'ame Mfg.
Model Mfg.
Model S/N S/N Type
" Size
- 'Type Size Weight Mounting Method
~ Weight Mounting Method Required Torque a
v Torque P
~II i,"~0 Power requirements:
(include
- normal, maximum and minimum).
Press Temp
. ~
~
Electric al Flow Max XP across valve Closing time 9 max 7P Opening time 9 max hP Power requir ements for functional accessories, (if any}
. Other:
L.3 Pneumatic
[3 Hydraulic List control signal inputs:
List functional accessories:*
n III. FUNCTION l.
Briefly describe'components normal and safety functions:
2.
The cceponents normal state is:
3.
Safety function:
L
- a. 'lj Emergency reactor shutdown f] Operating
[] Standby b.
t'3 Containment heat removal c.
-Q Containment isolation e.
$] Reactor core cooling d.
t;3 Reactor heat removal L] Prevent significant release of radio-
'active material to environment gn t') Goes the component function to mitigate the consequences of one or more of the following events7 f] Yes t,] No If "Yes", identify.
[3 LOCA tj Other t3 mSLB 4.
Saf ety requirements:
L] Intermittent Operation t.j Ouring postulated event t] Continuous Operation t] 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.)
FunctionaI accessories are those sub-components not,supplied by the manufactuier that are required to make the valve assembly operational, (e.g., limit switches).
5.
For VALVES:
does the component
[] Fail open
[] Fail closed
[] Fail as is
~ +
Is this the fail safe position?
[] Yes
[] No Is the valve used for throttling purposes?
[] Yes
[] No Is the valve part of the reactor coolant pressure boundary?
[] Yes
, [] No Ooes the valve have a specific limit for leakage?
f] Yes
[] No If "Yes"'ive limit:
IV.
gUALIFICATION 1..
Reference by specific number those applicable sections of the design codes and standards applicable to the component:
2.
Reference those qualification standards, used as a guide to
~
'ualify the component:
3.
Identify those parts of the above qualification standards deleted or modifieB in. the qualification progr am.
Oeleted:
Modified:
4.
Have acceptance criterias been established and documented in the test plan(s) for the component?
{ ] Yes
[] No 5.
What is the expected failure mode that would keep the pump or valve assembly from performing its safety function?
6.
Are the margins* identif ied in the qualification documentation?
[] Yes
[] No 1
d.
Margin is the difference between design basis parameters and.the test parameters used for equipment qualification.
If component is a
PUHP, complete IV.7.
a If ccmponent is a VALVE, ccmplete.IV.S.
r I
7.
Pump operability has been demonstrated by:
[3 Analysis
{l Test f] Canbination
~<'a Identify PUMP tests performed:..
[3 Shell hydrostatic
. b." fj Bearing temperature (ASHE Section III) evaluations c.
[] Seismic loading e.
[j Exploratory vibration (Fundamenta) free.
)
g.
{1 Aging: [].Thermal Q Mechanical
.'Q Pipe reaction end
'loads (nozzle loads3 k.
[] Extreme environment:
{] Humidity
[] Chemical d.. [] Vibration levels f.
f] Seal leakage 9 hydro press h.
[3 Flow performance Are curves provided [] Yes
[1 No j.
[] Others
{'3 Radiation 8.
Valve'perability has been demonstrated by: [] Analysis
[3 Test
[3 Combination Identify VALVE tests performed:
a.
f] Shell hydrostatic b.
(ASHE Section III)
[] Cold cyclic List times:
Open Closed c.
[] Seismic loading d.
f] Hot cyclic List times:
Open Closed e.
[] Exploratory vibration f.
(Fundamental free.
)
[j Main seat leakage g.
[] Aging: [] Thermal h.
[] Mechanical
[] Sack seat leakage k.
[] Pipe reaction end 1
loading
[] Extreme environment l.
[] Humidity
[] Chemical
[] Radiation
[] Disc hydrostatic
~ [] Flow interruption capability m.
[] Flow characteristics n.
[] 0th'ers Are curves provided?
[] Yes [] No 9.
As a result of any of the tests (or analysis),
were any deviations from design requirements identified? [] Yes [] No If "Yes", briefly describe any changes made in tests (or
'nalysis) or to the component to correct the deviation.
'I 10.
Was the test component precisely identical (as to model, size, etc.) to the in-plant component?. [] Yes [] No If "No", 'is installed component [] oversized.or [] undersized?
ll. If ~t e test was used to qualify the component, does the type test meet the requirements of IEEE 323-1974, Section 5.?
[] Yes [] No 12.
Is component orientation sensitive?
[] Yes [] No [] Unknown If "Yes", does installed orientation coincide with test orientation?
[] Yes [] No 13.
Is the component mounted in the same manner in-plant as it was during testing (i.e., welded, same number and size bolts, etc.)
[] Yes [] No [] Unknown
9 1~
Were the qualification tests performed in sequence and on ~onl
'one component?
L] Yes
[] No
,.I'f "Yes" identify sequence, (e.g., radiation, seismic, cyclic,-
thermal, etc.):
15.
If "aging"* was performed, identify the significant aging
. mechanisms:
16.
Identify loads imposed (assumed) on the component for the qualification tests (analysis) performed:
a.
L] Plants (shutdown loads) b.
[] Extreme environment c.
[] Seismic load d.
[] Others I
t
'17.
Have component design specifications been reviewed in-house to assure they envelope all expected operating, transient, and
...accident conditions?
(] Yes f] No
'8.
Does the component utilize any unique or special materials?
.(Examples are special gaskets or packing, limitations on nonferrous materials, or special coatings or surfaces.)
[] -Yes L] No If "Yes",
identify:'9.
Does component require any special maintenance procedures or practices, (including shorter periods between maintenance).
f] Yes [] No If "Yes", identify:
20.'s the qualified life for the component less than 40 years?
f] Yes [] No If "Yes", what i s the qual ified 1 ife?
As outlined in Section 4.4.1 of IEEE-627 1980.
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