ML20125E528
| ML20125E528 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/11/1985 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8506130149 | |
| Download: ML20125E528 (50) | |
Text
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Put$c Serwce Ektre aM Gas Company 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAf LING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L. Mitti General Manager Nuclear Assurance and Regulation June 11, 1985 Director of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:
Mr. Walter Butler, Chief Licensing Branch 2 Division of Licensing Gentlemen:
SER OUTSTANDING ISSUE NO. 2 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Pursuant to Hope Creek Generating Station Safety Evaluation Report (SER) Outstanding Issue No. 2, described in SER Section 3.10, Public Service Electric and Gas Company is incorporating the requested information, which was provided in a previous letter (R. L. Mittl to_A. Schwencer dated August 20, 1984), into FSAR Sections 3.9, 3.10 and 3.11.
It should be noted, the information being incorporated into the PSAR has been revised to reflect the comments received on February 11, 1985 (A. Schwencer to R.
L.
Mittl letter) with the exception of including the extent to which the draft standards ANSI /ASME ONPE-1 (N551.1), ONPE-2 (N551.2), ONPE-3 (N551.3), ONPE-4 (N551.4) and N41.6 and issued standard ANSI /ASME B.16.41 are used.
This information will be pro-vided by August 15, 1985.
The attached FSAR changes will be incorporated into Amendment 11 of the HCGS FSAR.
Should you have any questions in this regard, please contact us.
Very truly yours,
/
hV/
fgj610149850611 E
DOCK 05000354 I
9/3 The Energy People 95 4912 (4W I 83
(
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- Director of: Nuclear.
ns
. Reactor Regulation 2
6/11/85 Fb
_ 'C,
D. H. Wagner.
USNRC' Licensing ~ Project. Manager
.A.'R..Blough USNRC Senior-Resident Inspector I
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d HCGS FSAR Following adoption of any corrective measure, the piping system is again tested under the same conditions and evaluated for compliance with the acceptance criteria.
i 3.9.2.3 Seismic Qualification of Safety-Related NSSS Mechanical Eauipment This section describes the criteria for seismic qualification of safety-related mechanical equipment and the qualification testing and/or analyses applicable to this plant for all the major components on a component-by-component basis.
In some cases, a module or assembly of mechanical and electrical equipment is qualified as a unit, e.g., the emergency core cooling system (ECCS) pumps.
These modules are generally discussed in this section.
Seismic qualification testing for active pumps and valves is also discussed in Section 3.9.3.2.
Electrical supporting equipment, such as control consoles, cabinets, and panels, that are part of the NSSS, are discussed in Section 3.1Q.
The seismic test and/or evaluation results for safety-related mechanical equipment are maintained in a permanent file by GE and are readily auditable in all cases.
3.9.2.3.1 Tests and Analysis Criteria and Methods The ability of equipment to perform its safety-related function during and after an earthquake is demonstrated by tests and/or analyses.
Selection of testing, analysis, or a combination of the two is determined by the type, size, shape, and complexity of the equipment being considered.
When practical, the safety-related operations are performed simultaneously with
. vibratory testing.
Where this is not practical, operability is demonstrated by mathematical analysis, itN.scR T1.
quipment that is large, simple, and/or consumes large amounts of power is usually qualified by analysis or static test to show that the loads, stresses, and deflections are less than the allowable maximums.
Analysis and/or testing are also used to show there are no natural frequencies below 33 hertz.
If a natural frequency lower than 33 hertz is discovered, dynamic tests may be conducted and, in conjunction with mathematical analysis, used to verify operability and structural integrity at the required seismic input conditions.
3.9-41
INSERT 1 The MSSS seismic qualification program for scGS utilizes seismic data generated over a number of years.
Since it was j
not a licensing requirement at the time, most of these data were developed in earlier years without pre-aging or sequential testing of the equipment.
Bowever, NSSS. equipment located in harsh environments that has been qualified in recent years has l
generally been pre-aged and sequentially tested in accordance with the guidelines of IEEE 323-1974.
NSSS equipment on HCGS is being seismically evaluated using pre-aged and sequential testing data where it is available.
otherwise, the earlier data vihout pre-aging and sequential.
testing are being used.
The aging requirement is described in Section 3.11.2.7.2.
Maintenance and surveillance program requirements given in Section 3.11.2.7.6 incorporate the results of testing, as applicable.
When the equipment is qualified by dynamic test, the response spectrum or the time-history of the attachment point is used in determining input motion.
4 Natural frequency may be determined by running a continuous sweep frequency search using a sinusoidal steady-state input of low i
magnitude.
Seismic conditions are simulated by testing using random vibration input or single frequency input within equipment capability at frequencies up to 33 hertz.
Whichever method is used, the input motion during testing envelops the actual input motion expected during earthquake conditions.
The equipment being dynamically tested is mounted on a fixture that simulates the intended service mounting and causes no dynamic coupling to the equipment.
i Equipment having an extended structure, such as a valve operator, is analyzed by applying static equivalent seismic safe shutdown earthquake (SSE) loads at the center of gravity of the extended structure.
In. cases where the equipment structural complexity makes mathematical analysis impractical, a static bend test is used to determine spring constant and operational capability at I-li maximum equivalent seismic load conditions.
13.9.2.3.1.1 Random Vibration Input When random vibration input is used, the actual input motion envelops the appropriate floor input motion at the individual modes.
However, single frequency input, such as sine waves, can be used provided one of the following conditions are met a.
The characteristics of the required input motion are dominated by one frequency i
b.
The anticipated response of the equipment is adequately represented by one mode i
l c.
The input has sufficient intensity and duration to excite all modes to the required magnitude, such that I
the testing response spectra envelops the corresponding response spectra of the individual modes.
1 1
3.9-42
(Pago 1 cf 2)
INSERT 2
~
RPV and attached piping and pipe-mounted equipment are analyzed for annulus pressurization loads in the range of 60 i
to 100 Hz frequency depending on the dynamic characteristics of the equipment and its installation.
The of fact of hydro-dynamic loads is limited to the torus and torus attached -
piping in accordance with the Mark I containment Long-Term Program (NUREG 0661).
The qualification test frequencies, in general, range up to 50 Hs, which is the upperbound hydrodynamic 1
loading frequency.
l Non-ASME B4PV code camponents are qualified by tests that address the " strong motion" phase of seismic (and, if applicable, SRV) dynamic motion sufficient to generate the maximum equipment response.
This testing generally consists of five OBE tests and one SSE test of 30 seconds each.
Non-ASME B&PV code camponents are also qualified by analyses that have not considered vibra-tion fatigue-cycle of facts.
Some equipment is shown to be qualified by single-axis and/or single-frequency testing.
However, all essential equipment is reevaluated for seismic qualification according to the require-monts or recomumendations of IEEE 344-1975, Regulatory Guides 1.92 and 1.100, and Standard Review Plans 3.9.2, 3.10, and HCGS specific requirements.
In most instances, use of single-axis test data is restricted to equipment with a response that shows a predominant single mode of vibration in each direction with minimal crees coupling.
In some cases, if the response shows a single mode of vibration in each direction but also has cross coupling, the esisting single-axis test data are still used if the test response spectra (TRS) can be shown to exceed the required response spectra (RRS) by a factor of 1.4 over all frequencies.
In most instances, use of single-frequency test data is restricted to cases where the required igut motion is dosainated by one frequency, diere response of the equipment is adequately repre-sented by one mode, or where the igut motion has aufficient intensity and duration to produce sufficiently high levels of stress to assure structural integrity where structural integrity is the detenminant requirement.
In some cases, if the igut motion is sufficiently high so as to excite secondary sodes, such that modal responses can be shown to occur out of phase and at high enough levels, existing single-frequen.cy test data are also used to demonstrate operability.
K69/12-2
(Pago 2 cf 2)
INSERT 2 (Continued)
. The determination of which dynamic loads to address _ in a quali-fication program is made on the basis of both load evaluations made on similar designed f acilities and on plant-specific assessments.
From this basis, those loads which are considered
.to be significant are then selected and used in the qualification demonstration program.
As described in the NRC approved NEDE-24326-1-P operational aging, vibration aging for pipe-sounted equipment, applicable dynamic event aging, etc. are all consi-de red.
Specific loads, such as those generated for the sudden closure of valyes, have been considered when they are determined to be critical (i.e., loads from the closing of the SRVs and turbine stop valve are considered, but loads from the closure of a MSIV are not because of the relatively slow closure time of the MSIV).
Vibration fatigue-cycle ef fects for NSSS equipment designed to ASNE B&PV Code requirements are evaluated in a manner found satisfactory to NRC consultants.
The approach taken encompasses oss, SRV where applicable, thermal, and pressure cycles (see References 3.9-18, 3.9-19 and 3.9-20).
Table 3.9-2.7 (SQRT devices) provides a listing of typical NSSS equipment showing the methods used for their qualification.
l 569/12-3
HCGS FSAR 10/83 accelerations caused by the OBE and the SSE in conjunction with other normal operating loads.
Seismic qualification criteria used for the Seismic Category I mechanical equipment, with the exception of pumps and active valves, are in compliance with Regulatory Guide 1.100 and IEEE 344-1975.
The seismic qualification of pumps and active valves is discussed more fully in Section 3.9.3.2.
E The criteria for selecting a qualification method, by analysis and/or by test, is based on the practicality of the method for the function, type, size, shape, and complexity of the equipment.
Table 3.9-7 list all non-NSSS Seismic Category I mechanical equipment, equipment locations and qualification methods.
3.9.2.4.2 Methods and Procedures for Qualifying Non-NSSS Mechanical Equipment Seismic Category I equipment is shown to be capable of withstanding the horizontal and vertical accelerations of five OBEs and one SSE by dynamic analysis, dynamic testing, or a combination of dynamic analysis and testing.
The seismic qualification methods and procedures are in compliance with the requirements of IEEE 344-1975 and Regulatory Guide 1.100.
Pipe-mounted equipment is qualified by analysis and/or testing to the acceleration levels allowed for piping systems.
These levels include gravity and operation loading, as well as loading that is due to seismic or any other accident-related excitation, if applicable.
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3.9.2.4.2.1 Dynamic Analysis Dynamic analysis without testing is used if structural integrity alone ensures the intended design function.
Included is 3.9-49 Amendment 2
INSENT 3 tenere applicable, all equipment is pre-aged prior to seismic testing as part of the test sequence.
The aging requirement is described in Section 3.11.2.7.2.
Maintenance and Surveil-lance program requirements given irg Section 3.11.2.7.6 incorporate the results of testing, as" applicable.
INSERT 4 Applicable transient loads caused by sudden valve actuation (e.g., main stems turbine trips, HPCI turbine stop valve closure, MSSRV discharge,,etc.) are considered in the design loading of non-NSSS ASME camponents as specified in Table 3.9-8.
Force time histories of transient loads are developed using one of the computer codes referenced in Section 3.9.1.2.
These forcing functions are then input to the finite element piping analysis along with the applicable seismic response spectra.
The combined seismic and transient piping responses are evaluated against the equipment allowables specified for the appropriate service level.
Selected systems are subse-quently s@jected to in-plant dynamic transienti testing to confirm the acceptability of the analysis.
All pipe-mounced valve operators and accessories are qualified by using a sisigle amis, single frequency testing (required input motion (RIN) test).
This is justified on the grounds that the seismic floor motion is filtered through the piping system, Waich generally has one predaninant structural mode.
Thus the resulting motion that reaches the line-moisted equipment is predominantly a single frequency and single-axis motion.
The test is performed by using RIN in each of the three axes, independently.
In accordance with the Mark 1 Contairment Long-Term Program (NUR8G-0641), non-MSSS equipment attached to the torus has been evaluated for appropriate hydrodynamic loads, including iatigue effects.
Wetws11-to-drywell vacuum breakers inside the torus are also qualified for hydrodynamic loads for frequencies up to 50 Es.
_.e_.
HCGS FSAR on the allowable stresses set forth in the applicable codes.
d..
The allowable shear on anchor bolts set in concrete are in accordance with Table Number 26-1 of the Uniform Building Code.
Table 3.9-5d shows the calculated stress values and allowable stress limits for the heat exchangers.
3.9.3.1.20 Non-NSSS ASME B&PV Code Constructed Items The design loading combinations categorized with respect to plant operating conditions identified as normal, upset, emergency, and faulted for the non-NSSS ASME B&PV Code constructed items are presented in Table 3.9-8.
The design criteria and stress limits associated with each of the plant operating conditions for each type of ASME B&PV Code constructed item are presented in Tables 3.9-9 through 3.9-15.
The component operating condition is the same as the plant operating condition, except for active pumps or valves, for which the emergency or faulted plant condition is considered normal.
3.9.3.2 NSSS Puno and Valve Operability Assurance The NSSS active pumps are listed in Table 3.9-16 and the NSSS active valves are listed in Table 3.9-17. h6/e J.9 A s //s/s examples of tvonT N3AS dyuo*pmenr guaJ$eMoen methadology.
i Active mechanical equipment classified as Seismic Category I is designed to perform its function during the life of the plant under postulated plant conditions.
Equipment with faulted condition functional requirements include active pumps and valves in fluid systems such as the RHR system and the core spray system.* Active equipment must perform a mechanical motion during the course of accomplishing a safety function.
h#
Operability is, ensured by satisfying the requirements of the following programs.
Safety-related active valves are qualified I
by prototype testing and analysis, and safety-related active
'I 3.9-73
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The only Nsss active ~ valves subjected to hydrodynamic loads are the safety relief valves (B21-F013) and the main steam isolation valves (B21-F022).
Both of these valve types are i
being dynamically qualified by test up to 100 Hz.
The load and conditions considered in the qualification of safety-related pumps and valves are given in Tables 3.9-5 and 3.9-5(a).
Deflections due to piping loads and dynamic loads are addressed for active essential pumps and valves by several methods depending on the situation.
Methods used include static deflection analysis, dynamic deflection analysis, and dynamic seismic testing.
The method of qualification for sof t parts of safety-related pumps and valves is addressed in section 3.11.2.6.
In addition, maintenance and surveillance program requirements are given in section 3.11.2.7.6.
Periodic inspection and operational testing is performed as per the requirements in Chapter 16.
See Section 3.9.6 for operational testing outline.
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A K49/13-6
of the absence of natural frequencies below 33 hertz, and the ability to remain operable under a horizontal seismic coefficient of 6.5g and a vertical seismic coefficient of 4.5g at 33 hertz.
3.9.3.2.7 Non-NSSS Pump and Valve Operability Assurance 3.9.3.2.7.1 Non-NSSS Active Pumps The non-NSSS active pumps are tabulated in Table 3.'9-18.
Non-NSSS active pumps are subjected to testing both in the manufacturer's shop and following their installation to verify that they meet the criteria required by the respective design specifications.
/NstMQ During manufacture, nondestructive test procedures including liquid penetrant examination, radiographic examination, magnetic particle inspection, and ultrasonic inspection are applied to the t
All of these procedures are performed in accordance with pumps.
the ASME B&PV Code,Section II L I
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After the pumps have been assembled, they are hydrostatically and performance tested in the manufacturer's shop in accordance with i
j Hydraulic Institute standards.
After the pumps are instelled, they undergo functional tests.
Provisions are made for inspection and operational testing per the requirements in j
Chapter 16.A All of these tests demonstrate that the pumps are reliable and will function as specified.
In addition to the tests and procedures referred to above, the l
pumps are seismically analyzed to ensure that they will be
]
capable of operating both during and after OBE and SSE events.
> 1N$cR T &
n performing these analyses, conservative seismic accelerations and stress criteria are used; this ensures that critical parts of the pump are not damaged during a seismic event, and that the pump still operates following such an event.
sivs cftT pump / motor combination is designed to rotate at a constant
~
Eac speed under all conditions, unless the rotor becomes completely
- seized, i.e.,
fails to rotate at all.
Motors are designed to
{
withstand short periods of severe ove'eload and, typically, the rotor can be seized a short period of time before a circuit breaker shuts down the pump.
However, the high rotary inertia in 3.9-80 Amendment 8
INSERT 6 Table 3.9-2.9, provides exanples of Non-NSSS active pumps, indica-ting their qualification method and the industry standards met.
1 p
4 1
INSERT 7 f
The method of qualification for sof t parts of safety-related pumps is addressed in Section 3.11.2.6.
In addition, mainte-nance and surveillance program requirements are given in Section 3.11.2.7.6.
l INSERT S i
Information on loading combinations, system operating tran-i sients, and stress limits for pumps is given in the response to Question 210.52.
t l
IW8ERT 9
.l l
Deflection due to piping loads and dynamic loads is addressed for active essential pumps by several methods depending on l
the situation.
Methods used include static deflection analysis, 4
a dynaipic dynamic deflection analysis, static beng testing,l ecdM Wed satanic testing. % sadheds acceenaf W he j
- 4. % atpt.ean sf m a an a a u k w..s.I<- a e
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9
HCGS FSAR the operating pump rotor and t'he nature of the random, short-duration loading characteristics of the seismic event, will prevent the rotor from becoming seized.
In actuality, the seismic loadings will cause only a slight increase in the torque, i.e.,~ motor current, necessary to drive the pump at the constant design speed.
Therefore, the pump will not shut down during the event and will operate at the design speed, despite the seismic loads.
From previous discussions, it is evident that the pump / motor units will withstand seismic loadings and perform their intended functions.
These proposed requirements take into account the complex characteristics of the pump, and they are sufficient to demonstrate and ensure the seismic operability of these pumps.
Post-seismic condition operating loads will be no worse than the normal plant operating limits.
3.9.3.2.7.2 Non-NSSS Active Valves Non-NSSS active valves are tabulated in Table 3.9-19.
See Sections 3.9.3.2.5 and 3.9.3.2.6 for a discussion of operability assurance of active valves supplied by the NSSS vendor.
(/d.5ER T /0 Safety-related non-NSSS active valves are subjected to a series of stringent tests prior to service and during the plant life.
Before installation, the following tests are performed: the shell hydrostatic test, in accordance with ASME B&PV Section III requirements; backseat and main seat leakage tests; the disc hydrostatic test; functional tests which verify that the valve opens and closes within the specified time limits; and the operability qualification of motor, air, and hydraulic operators for environmental conditions over the installed life, i.e.,
aging, radiation, accident environment simulation, etc, in accordance with IEEE 382-1972.
After installation, cold hydrostatic tests, functional tests (in accordance with the requirements of Chapter 14), and periodic inservice operation (in accordance with the requirements of Chapter 16) are performed to verify and ensure the functional ability of the valve.de-~
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(Sea Sechon 314 f*r OP**HM*' '!**i'E9
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The valves are designed using either stress analyses or pressure-containing minimum wall thickness requirements.
For all active valves with extended topworks, an analysis is also performed for static equivalent SSE loads applied at the extended structure's center of gravity.
The maximum stress limits allowed in the analyses demonstrate structural integrity and are equal to the limits recommended by ASME for the particular ASME class of valve 3.9-81
INSENT 10 s
Table 3.9-19, provides examples of non-NSSS active valves, indi-cating their qualification method and the industry standards met.
INSERT 11 The method of qualification for sof t parts of safety-related valves is addressed in Section 3.11.2.6.
In addition, mainte-nance and surveillance program requirements are given in Section 3.11.2.7.6.
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In addition to the foregoing, a representative valve of each type is factory-tested to verify operability during a simulated seismic event.
The factory qualification testing procedures are u.2
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- 4 SERT IS
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l typical valve installations.
The valve unit includes the actuator and all appurtenances normally attached to the' valve in service.
The operability of the valve during an SSE is demonstrated by satisfying the following criteria:
a.
All active valves with topworks must have a first natural frequency greater than 33 Es.
This is ptoven by analyses.
For valves mounted on lines connected directly or indirectly to the RFV or the biological shield, resonant frequencies up to 100 herts are determined.
Such frequencies are used as input to the dynamic analysis of the piping systems for annulus N4.
e i
pressurization effects.
Because of the uni e
I heavier loads imposed by hydrodynami n piping attached to the suppression chamber, valves =o6eed f in '--
' l.:;;;
installed in such piping ; t: t':
C lo1geh) in M::t :
re additionally analyzed to determine all
~
k resonant frequencies between 0 and 100 herts.
Such I
YJpAmfL frequencies are used as input to the dynami nalysis lead $
of these piping systems.
Qg gg gg 4 j ;n Table S.iOR b.
While in the shop and installed in a suitable test rig, the extended topworks of the valve are subjected to a statically applied equivalent seismic load.
The load, specified as 4.5 g times the weight of the topworks, is direction of the weakest axis of the yoke.pworks in the applied at the center of gravity of the to The design J
pressure of the valve is simultaneously applied to the valve during the static load tests.
The valve is then' operated at the minimum specified c.
actuation supply voltage or air pressure, with the equivalent seismic static load applied.
The valve must i
perform its safety related function within the specified operating time limits.
~
3.9-82
INSERT 12 The loads and' conditions considered in the qualifica't' ion of class 1 valves are given in Table 3.9-10.-The loads and conditions considered for Class 2 and 3 valves are given in Table 3.9-15.
INSEAT 13 Deflection due to piping loads and dynamic loads are addressed for active essential valves by several methods depending on Methods used :sncluds static deflection analysis, l
the situation.
dynamic deflection analysis, static bend testing, and dynamic seismic testing.
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HCGS FSAR 6/84 3.9-16 General Electric, Analytical Model for Loss-of-Coolant Analysis in Accordance with 10 CFR 50, Appendix K, NEDO-20566, April 1977.
3.9-17 General Electric, Boilina Water Reactor Feedwater Nozzle /Sparcer Final Report, NEDO-21821, March 1978.
Add Inserl '4 3.9.117 Amendment 6
INSERT 14 3.9-18
' Letter fr a W. G. Gang (GE) to R. Sosnak (NRC) dated January 15, 1981 on the subject of "GE Position and Fatigue Analysis ".
3.9-19 Letter fra R. J. Bosnak (NRC) to W. G. Gahg ( GE )
dated Foruary 19, 1981 on the subject of
" Fatigue Analysis".
3.9-20 Letter from R. B. Johnson (GE) to R. Bosnak (NRC) dated June 29, 1981 on the subject of "GE Position on Fatigue Analysis".
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g HGIS FSAR 1hE.E 3.9-27 1YPICE NSSS SGtt IOJIPsENT QUALIFEATION EDanrrumy Qualification, MPL.
Nuuher F4uignent Methodology E15-8001 MR heat etcharger Resgones spectrum dynamic analysis B11-C002 MR pump motor Resgones spectrum dynamic analysis I
E21-C001 Reactor core sgray puup Resgones spectrus dynamic analysis C41-C001 Stardby liquid control pump Static analysis / Dynamic test -
IEEE 344-1975 C41-A003 SIC aca==dator Static analysis C41-A001 SII tark Static analysis to 1.75g E41-G02 HCPI turbine Dpanic test E51-C002 RCIC turbine Dynamic test 145C3103 1herscsuster Static analysis 145C3224 Temperatare elesant miti-frequency, multi-axis test 159C4361 Imvel switdt Sirgia axis, single frequency test 163C1303 Ltsit stitch Sirgle frequency - sulti-axis test f
e ass /n 1
HOGS FSAR 1NLE 3.9-2F DUWUUS OF NSSS PVGtt EUIPfelT QUALIFEATION M5H000 LOGY
- Peg, Qualification, mmber Radignant Methodoloay _
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E91-C001 rPCI pap Static analysis fbr dynanic analysis C51-J004 Guide ttbo valve Sirgle frequency - static analysis B21-F013 SW Static analysis, comparison to other B21-F022/
Pti1V Sirgle misMti-axis test F028 C11-F009/
CID solenoid w1ve Sirgle amisMti-axis test F182
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Page 1 cf 2 HCGI FSAR TABLE 3.9-27 i
cueguS & Non NSSS PNDRT IQUIPPElNT QLALIFICATION METHODOECGY equipsont Qualificstion Number Description Method Standards (1) f
~ 1A,kFPR10 SACS Ptap Static A,F,I IC, 3D-7210 Analysis 1A, IFM11 Fuel Pool Static A,F,I coolirg Ptap Analysis 1A, IFM02 Motor Driven Static F
IC, ID-M02 Diesel Fuel Analysis Oil Pump 1A, IFP23 BCC5 Jodey Static A, F, I IC, ID-P220 Ptap Analysis 1A, 1>M14 Otilled Water Dpasic A,F,I circulation Ptaqp Analpis 1A, IbMOS Engine-Driven Dpaic-F IC, ID-MOS Jacket Mter Ptap Analpis IA, IFP507 Spray hter Static A, F, I '
IC, ID-P507 Bocater Ptap Analpia 1-BC-W-F047A 18"-GMME-40 Static Analysis A, E, F, I
& Dpanic Testirg
& Pull Test 1-9 tmM031A 4"MBIHB-te Static Analp is A, E, F, I
& Dpanic Testing
& Pull Test 1-PNN-POS9 10"-IB > G M O Static Analpia A, E, F, I
& Dyanic Testing
& Full Test 1-EEHRH655 6"-teC-GE-AD Static Analpis A, E, F, I
& opanic Testirg
& Pull Test 1-AIH W-P019 3"-IBh-GMD Static Analysis A,E,F,I
& Dynamic Testirg
& Pull Test 1-AB-tmM0744 24"-DUNX-AD Static Analpis A, E, F, I A
& Opasic Testisg
& pull Test E69/13-3
Page 2 cd! 2 HCGI FTAR TABt2 3.9-19 (Cont'd)
EuMPIES & Non-ItiSS Pe>Rt EUN9ENT QmLIFICATION MED1000IIIiY Equipannt Qualification, Number ~
Descriptio,n Method Standards (1) 1-BD-HV-F046 2"-CBMilHO Static Analysis A,E,F,I
& Dynamic Testirg
& Pull Test
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& Dynamic Testirg
& Pull Test 1-IG-W-23954 8"-leC-BF-AD Static Analysis A,E,F,I
& Dynamic Testirg
& Pull Test l-EA-W-2356A 20"-tisc-BF-fD Static Analysis A,E,F,I
& Dynamic Testieg
& Pull Test i
(1) Standards A - IEEB-34+ 1975 F - AINE B&PV Code,Section III I - NRC Regulatomy Guide 1.100, Ber.1 E - IEEE 382, B 72 K69M 4
. HCGS FSAA TABLE 3.9-Jo Non-NSSS VALVES SUBJECTED TO HYDRCDYNAMIC LOADS i
1-BE-HV-F001A to D 1-FC-HV-F059 l-BJ-HV-F042 1-FD-HV-F071 1-EE-HV-4680 1-EE-HV-46 81 1-BD-HV-F031 f
1-SC-HV-F004 A to D 1-EE-HV-4652
~
1-EE-HV-467 9 1-GS-W-4958
~
l-BE-HV-F015A and B 1-SC-HV-F024A and 3 1-BC-HV-4421 1-BC-HV-4420A and B l-BE-HV-F031A 1-BJ-HV-F012 1-FD-HV-F079 1-FD-W-F075 1-BC-HV-F007C 1-AB-PSV-F037A to N 1-AB-PSV-F037J to M l-AB-PSV-F037P, Q, R l-AB-PSV-4500 A to H 1-AB-PSV-4500J to H 1-AB-PSV-4500P, Q, R 1-BD-SV-F019 l-GS-PSV-4946 A to H
=
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a69/11-5
.,y.
HCGS FSAR 3.10.1.1.2 Seismic Category I Non-NSSS Equipment Identification
' Non-NSSS safety-related instrumentation and Class IE electrical equipment that requires seismic qualification are identified in Tables 3.10-1 and 3.10-2, respectively.
3.10.1.2 Seismic Desian Criteria 3.10.1.2.1 Seismic Design Criteria (NSSS)
I EfA Seismic Category I instrumentation and electrical equipment are designed to withstand the safe shutdown earthquake (SSE) defined in Section 3.7.1.
The seismic criteria used in the design and subsequent qualification of a11' Class 1E instrumentation and electrical equipment supplied by GE are as described below.
The Class 1E equipment is capable of performing all safety-h related functions during normal plant operation, anticipated transients, design basis accidents (DBAs), and post-accident 4
operation, while being subjected to, and after the cessation of, the accelerations resulting from the SSE at the point of attachment of the equipment to the building or supporting structure.
The criteria for each of the devices used in the Class 1E systems depend on the use in a given system.
For example, a relay in one system may, as its safety function, have to deenergize and open its contacts within a certain time, while in another system, it must energize and.close its contacts.
Since General Electric (GE) supplies many devices for many applications, the approach taken was to test the device in the worst-case configuration.
In this way, the capability of protective action initiation and the proper operation of safety-failure circuits are ensured.
From the basic input ground motion data, a series of response curves at various building elevations are developed after the building layout is completed.
This information is included in 1
the purchase specifications.for Seismic Category I equipment.
Suppliers for equipment such as batteries and racks, instrument racks, control consoles, etc, are required to submit test data, 3.10-2 i
a I
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1 INSERT 15 The MSSS seismic qualification program for BCGS utilizes Since it was l
seismic data generated over a number of years.
not a licensing requirement at the time, most of these data were developed in earlier years without pre-aging or sequential However, NSSS, equipment located in testing of the equipment.
harsh environments that has been qualified in recent years has generally been pre-aged and sequentially tested in accordance with the guidelines of IEEE 323-1974.
NSSS equipment on HCGS is being seismically evaluated using j
i pre-aged and sequential testing data where it is available.
Otherwise, the earlier data vihout pre-aging and sequential.
testing are being used.
The aging requirement is described in Section 3.11.2.7.2.
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demonstrate compliance with Regulatory Guide 1.100.
However, the f
1 seismic qualification requirements used for this plant ensure an adequate degree of equipment performance and thereby represent an acceptable basis for qualifying the equipment.
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3.10.2.1.1 Procedures l
GE-supplied Class IE equipment meets the requirement that the qualification should demonstrate the capability to perform the
]
required function during and after the effects of the safe shutdown earthquake (SSE).
Both analysis and testing are used, j
but most equipment is tested.
Analyses are primarily used to determine the adequacy of mechanical strength,*e.g., mounting bolts, etc, after operating capability is established by testing as follows:
1 a.
Analysis - GE-supplied Class 1E equipment performing primarily a mechanical safety function, e.g.,
pressure boundary devices, etc, is analyzed since the passive nature of their critical safety role usually makes testing impractical.
Analytical methods sanctioned by IEEE 344-1971 are used in such cases.
See Table 3.10-3 for indication of which items were qualified by analysis.
I b.
Testing - GE-supplied Class 1E equipment having primarily an active electrical safety function is tested in compliance with IEEE 344-1971, Section 3.2.
3.10.2.1.2 Documentation Available documentation verifies that the seismic qualification of GE-supplied Class 1E equipment is in accordance with the requirements of IEEE 344-1971, Section 4.
3.10.2.2 Testina Procedures for Qualifyina NSSS Electrical Eauipment and Instrumentation, Excludina Motors and Valve-Mounted Eauipment i
The test procedures require that the device be mounted on the table of the vibration nachine in a manner similar to the actual mounting condition.
Tre device is tested in the operating states as if it were performing its Class IE functions.
These states l
i 3.10-4
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INSERT'16 Some equipment is shown to be qualifled by single-axis and/or single-frequency testing.
However, all essential equipment is reevaluated for seismic qualification according to the require-monts or recommendations of IEEE 344-1975, Regulatory Guides
- l.92 and 1.100, and Standard Review Plans 3.9.2, 3.10, and HCGS specific requirements.
In most instances, use of single-axis test data is restricted to equipment with response that shows a predominant single mode of vibration in each direction with a minimal cross coup-ling.
In some cases, if the response shows a single ande of vibration in each direction but also has cross coupling, the existing single-axis test data are still used if the test response spectra (TRS) can be shown to exceed the required response spectra (RRS) by a f actor of 1.4 over all frequencies.
In most instances, use of single-frequency test data is res-tricted to cases where the required input motion is dominated by one frequency, where response of the equipment is adequately j
represented by one mode, or where the input motion has suffi-cient intensity and duration to produce sufficiently high levels of stress to assure structural integrity where structural integ-rity is the determinant requirement.
In some cases, if the input motion is sufficiently high so as to excite secondary modes, such that modal responses can be shown to occur out of phase and at high enough levels, existing single-frequency test data are also used to demonstrate operability.
l i
K69/12-17
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The summary of the tests on the devices used in Class 1E applications given in Table 3.10-3 includes the qualification limit for each device tested.
The above procedures are required of purchased devices as well as those made by GE.
Vendor test results are reviewed, and if unacceptable, the tests are repeated either by GE or the vendor.
If the vendor tests were adequate, the device is considered qualified to the limits of the test.
3.10.2.3 Methods and Procedures for Qualifyino Non-NSSS
- Instrumentation and Electrical Eauipment-7 /qs(AT ID The~anaI9 sis and testing for the seismic qualification of non-NSSS Class 1E instrumentation and electrical equipment are in compliance with the appropriate project seismic specifications that meet the requirements of IEEE 344-1975 and Regulatory Guide 1.100.
Pipe-mounted instrumentation is qualified by analysis and/or testing to the acceleration levels allowed for piping systems.
These levels include gravity and operation loading, as well as loading that is due to seismic or any other accident-related Axcttation J applicable.
C; >sNscAT* / 8
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Seismic ~ Category I equipment is shown to be capable of withstanding the horizontal and vertical accelerations of five OBEs and one SSE by dynamic analysis, dynamic testing, or a combination of dynamic analysis and testing.
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"h;;;;u:11; pr: tided er th: teru; sh:11 for t;;;;r;ture meriteriag era =lec qualifi:d for hydrodyn;;ic 10;d; f r frequencier up te 50 Me_
3.10.2.3.1 Dynamic Analysis Dynamic analysis without testing is performed as a basis for qualification only if the necessary functional operability of the i
equipment is ensured by its structural integrity alone.
For this analysis, equipment is idealized using a mathematical model in which frequencies and mode shapes are determined for vibration in the vertical direction and two orthogonal horizontal directions.
For each direction of vibration, the spectral accelerations per mode are obtained from the appropriate response spectrum curve corresponding to the location and damping of the l
equipment.
3.10-6 Amendment 2
INSERT 17' mere applicable, all equipment is pre-aged prior to seismic testing as part of the test sequence.
The aging requirement is described in Section 3.11.2.7.2.
Maintenance and surveil-lance progran requirements given in Section 3.11.2.7.6 incorpgate the results of testing, as applicable.
or' INSERT 18 All pipe-mounted control valve operators and accessories are qualified by using a single axis, single frequency test (required input motion (RIM). test).
This is justified on the grounds that the seismic floor motion is filtered through the piping system, which generally has one predominant structural mode.
Thus the resulting motion that reaches the line-mounted ~
equipment is predominantly a single-frequency and single-axis motion.
The test is performed by using RIM in each of the three axes, independently.
=
INSERT 19 In accordance with the Mark I Containment Long-Term Program (NURsG-0661), non-leBSS equipment attached to the torus has been evaluated for appropriate hydrodynamic loads, including fatigue effects.
Themowella provided on the torus shell for temperature monitor-t ing are also qualified for hydrodynamic loads for frequencies up to 50 Hz, including f atigue effects.
K69/12-18 ne.
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i NCf48 FSAR 1 of 2 TAB &B 3.18-1 SEISMIC Ouhl.IFICATION TEST SINemRE NEM -ESSS I N TRIB E N N l
Itsus Qualiftestion Standards h
M Description Area / Elevation Supplier Method (1)
J-3000 Main control panels Main Control run/137ft, teiley that & analysis A,1 control e s t rum /193ft J-2010 Rosete control panele various Consip/
Test & analysis A,I Custom 11ae
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J-3010 Electronic field tramesdt-various Tober Test A,I ters J-3090 femel-mounted instruments verloos westinghouse Test A,1 i
5*#2 analyser monet b1dg/162 ft Consip Delphi Test & analysis A,I J-3590 2
J-3710 mediation monitoring various Tac Test A,1 J-4830 F1eed alarms various Fluid C (FCI)
Test A,I J-5250 Pressere indicators various Dresser Test AI J-5540 temp wells, MFro various Thermo Stet & analysis A,I Electric J-6410 control valves various Masomellem Test & analysis A F,I J-6830 Solenoid valves verloos Valcor Test & analysis D,F i
J-4850 control butterfly valves various Fisher Test & analysis F
i-J-4100 Pressere regulators Various Marotta Test A,1 l
J-7030 anoses flow check valves verloos Dragon Test F
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.i Omalification Standards Item g
Dooeristion Area /Blevation Suse11er seethod (1) i U
F1990 sypass malfelds Various Dragon Analysis F
J-7300 Fiesible metal hoes various sental Bellows that A,I
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3-8100 amargency load esquenos Ama 130' e" consolidated Test a,I controle j
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HCGS FSAR 5/85 Radiation exposures to components will be minor and will be due to two sources: radiation shine, and immersion in airborne radioactivity released in a controlled manner from the reactor building.
The TID from both sources will be less than 100 rads for 180 days.
3.11.1.3 Excluded Systems - NSSS and Non-Ng1S l
Table 3.11-8 shows the systems designated as seismic Category I in Table 3.2-1 that are to be excluded from the HCGS Environmental Qualification Program.
The table identifies each system with correlation to Table 3.2-1 and the reason for exclusion from the HCGS Environmental Qualification Program.
3.11.1.4 Environmental Conditions - NSSS and Non-NSSS l
The environmental conditions shown in Table 3.11-1, and the associated figures may be changed at a later date because of-continuing evaluations that are being performed on a case by case basis.
3.11.2 QUALIFICATION TESTS AND ANALYSES 3.11.2.1 NSSS Safety-Related Class 1E Electrical Eauipment Harsh Environment Qualification Components of the nuclear steam supply system (NSSS) Class IE electrical equipment are qualified in accordance with the environmental qualification criteria and guidelines specified as Category II in NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," dated December 1979 (for comment), and IEEE-323-1971, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations."
However, the HCGS environmental qualification program is attempting to upgrade qualification of equipment to the requirements of NUREG-0588, Category F.fand rat.s23-/ try Components of the NSSS Class 1E electrical equipment in a harsh environment are qualified by test, analyses, or a combination thereof.
Those components used in more than one system, which can be or are located in different plant areas, are tested or 3.11-4 Amendment 10 T
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\\n 3.11.2.2.6 Regulatory Guide 1.40, Qualification Tests of Continuous-Duty Motors Installed Inside the i
Containment of Water-Cooled Nuclear Power Plants Regulatory Guide 1.40 is not applicable to the HCGS because there r-are no NSSS-supplied continuous-duty, safety-related motors
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inside the primary containment.
5 3.11.2.2.7 Regulatory Guide 1.73 - Qualification Tests of Electrical Valve Operators Installed Inside the Containment of Nuclear Power Plants Regulatory Guide 1.73 is not applicable to HCGS because there are L
no NSSS-supplied electric motor-operated valves inside the primary containment.
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3.11.2.2.8 Regulatory Guide 1.89 - Qualification of Class 1E i
i Equipment for Nuclear Power Plants I
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Hope Cree,k Generating Station will attempt to comply on a case by
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case basis.
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3.11.2.3' Non-NSSS Class 1E Electrical Eouipment Harsh Environment Oualification 4
1 Harsh environment qualification of Class 1E equipment is accomplished by test or analysis (where analysis is supported by test data or otherwise justifiable) for the applicable environmental conditions postulated to exist at the equipment
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location.
These components are qualified to the requirements of I
IEEE 323-1971 and NUREG-0588, Category II.
However, the HCGS environmental qualification program is attempting to upgrade to
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NUREG-0588 Category I requirements.
E anol rCES 323-/979 R
5 The identification, location, and conditions to which non-NSSS 3
supplied IE equipment is required to function will be shown in a i
1 separate environmental qualification report.
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-3.11.2.4 Regulatory Guides and General Desion Criteria -
2 Non-NSSS Eouioment j
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3.11-6 Amendment 7
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