ML20070V281

III Seismic Qualification Review Team Visit Rept (Second Visit)

ML20070V281
Person / Time
Site:	Waterford, 05000000, Shoreham
Issue date:	12/13/1982
From:	Macek R, Singh J EG&G, INC.
To:	NRC
Shared Package
ML082480769	List: ML20069A592 ML20069A653 ML20069A743 ML20069A761 ML20069A774 ML20069D186 ML20069P151 ML20070V135 ML20070V154 ML20070V171 ML20070V193 ML20070V203 ML20070V243 ML20070V245 ML20070V257 ML20070V270 ML20070V281 ML20070V287 ML20070V297
References
CON-FIN-A-6415 NUDOCS 8302170223
Download: ML20070V281 (43)

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ATTACHMENT III WATERFORD III i

SQRT VISIT REPORT i

(Second Visit)

J. N. Singh R. W. Macek M. J. Russell EG&G Idaho, Inc.

Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Under OLE Contract No. OE-AC07-76IO01570 FIN No. A6415 8302170223 830202

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4 ABSTRACT EG&G Idaho, Inc., has evaluated the Louisiana Power and Light Company's program for the dynamic qualification of safety related electrical and mechanical equipment ~for Waterford Nuclear Power Plant Unit 3.

In this progrei, the applicants use test or analysis or a combin'ation of both to qualify equipment, such that its safety function will be insured during and after the dynamic event and provide j

documentation. The initial review indicates that an appropriate qualification has been defined and initiated for seismic category I electrical and mechanical equipment. When completed, this would provide reasonable assurance that such equipment will function properly during and after the excitation due to vibratory forces of the dynamic event.

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ABSTRACT..............................................................

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l INTRODUCTION..........................................................

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BORIC ACID MAKEUP PUMP (NSSS-1).................................. - 3 2.

BORIC ACIO TANK CIRCULATING VALVE (NSSS-2).......................

4 3.

BORIC ACID PUMP DISCHARGE VALVE (NSSS-3).........................

5 4.

HO LDU P TAN K C ( N S SS-4 )...........................................

6 5.

FEEDWATER CONTROL VALVE (NSSS-5).................................

7 6.

RESISTOR INPUT CARD (NSSS-6).....................................

9 7.

INDICATOR (NSSS-7)...............................................

11 8.

RESISTANCE TEMPERATURE DETECTOR (NSSS-8).........................

13 9.

RCP SIGNAL PROCESSOR (NSSS-9)....................................

14

10. REACTOR TRIP SWITCHGEAR CABINET (NSSS-10)........................

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11. R EC O RD ER ( N S S S - 11 )...............................................

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12. CEDM REED SWITCH POSITION TRANSMITTER (NSSS-12)..................

20

13. PRESSURE TRANSMITTER (NSSS-13)...................................

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14. 20 1CVA INVERTER ( BOP-1)..........................................

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15. DIESEL GENERATOR LUBE OIL PIPING (BOP-2).........................

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16. LEVEL SWITCH ( BO P-3 ).............................................

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17. AXIAL FAN (BOP-4)................................................

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18. HVAC WATER PUMP (80P-5)..........................................

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19. G RAVITY DAMP ER ( BOP-6 )...........................................

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20. THREE INCH 150 LB OIAPHRAM VALVE (BOP-7).........................

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21. ONE INCH 2500 LB RELIEF VALVE (BOP-8)............................

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22. HALF-INCH GLOBE VALVE (BOP-9)....................................

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23. INDICATOR (BOP-10)...............................................

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24. CLECTRIC RELAY (BOP-11)..........................................

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FOUR INCH 300 LB GATE VALVE ( BOP-12).............................

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INTRODUCTION The Equipment Qualification Branch (EQB) of the Nuclear Regulatory Commission (NRC) has the lead responsibility in reviewing and evaluating the dynamic qualification of safety'related mechanical and electrical equipment. This equipment may be subjected to vibration from earthquakes' and/or hydrodynamic forces. Applicants are ' required to use test or analysis or a combination of both to qualify equipment essential to plant safety, such that its function will be ensured during and after the dynamic event. These pieces of equipment and how they meet the required criteria j

are described by applicants in a Final Safety Analysis Report (FSAR). On completion of the FSAR review, evaluation and approval, the applicant receives an Operating License (OL) for commercial plant operation.

1 A Seismic Qualification Review Team (SQRT) consisting of engineers from the EQB of NRC and Idaho National Engineering Laboratory (INEL), made a site visit to Waterford Unit 3 at Taft, Louisiana from August 30 through September 3, 1982. This team included a contingent of three from INEL as consultants to NRC. The purpose of the visit was to observe the field installation, review the equipment qualification methods, procedures (including modeling technique and adequacy), and documented results for a list of selected seismic Category I mechanical and electrical equipment and their supporting structures.

Following the site visit, EG&G personnel were to advise MC with respect to the adequacy of qualification of this i

equipment to perform its intended function. This is a preliminary report containing our findings. This report indicates which of the items are qualified and require no additional documentation.

It also identifies some equipment and certain general concerns for which additional information is needed in order for EG&G to complete the review. These are referred to as open items. The applicant is to further investigate and provide additional documentation to resolve these issues. A final version of this report will be issued after all the cutstanding issues are resolved.

Table 1 has the list of attendees and subsequent sections of this report give a brief' overview and identify our concerns, followed by our findings, for each of the selected seismic Category I equipment.

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TABLE 1.

LIST OF ATTENDEES

'l R. S. Alexandru EBASCO S. Black NRC T. Y. Chang NRC W. Cetta EBASCO J. DeBruin EBASCO L. Constable NRC A. Desphande EBASCO A. DeVito EBASCO R. J. Esnes EBASCO F. Drummond LP&L T. E. Fitzsimmons C-E(PE)

K. K. Gala LP&L J. Hart EBASCO A. Jones ESASCO J. Kealy EBASCO E. Livesy EBASCO M. Meyer LP&L R. W. Macek EG&G, Idaho T. MacNair C-E L. V. Maurin LP&L E. Miller W CCD B. Mowry IBASCO S. Nath EBASCO R. L. Novgrod LP&L s/u J. Pare 11o W RD l.

H. Parikh EBASCO R. Prados LP&L W. Ritter W IED M. J. Russell TG&G, Idaho Z. T. Shi EBASCO E. Siegel C-E J. N. Singh EG&G Idaho F. Sistino C-E R. K. Stampley EBASCO I. V. Sydoriak EBASCO V. Tokarz C-E (PE)

J. Tompeck EBASCO R. Vidal EBASCO M. G. Williams LP&L J. Zudans NUS i

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BORIC ACID MAKEUP PUMP (NSSS-1)

The boric acid makeup pump, supplied by Crane-Deming with Model No. 3065 A-50, is mounted with four 5/8 in. bolts in the chemical and volume control system at the minus 35 ft elevation of the reactor auxiliary building. The reference document for its qualification is the Mcdonald Engineering Co. report, ME-359 Certified Seismic Analysis Report of Crane-Deming End Suction Centrifucal pump, Figure 3065, Size A50, Revision 1, dated January 17, 1977.

ThepumpwasqualifiedbyastaticbeamanalysisusingtheICES-STRUOL computer code. 1.5 g accelerations were applied in both horizontal directions together vith 1.0 g acceleration in the vertical direction.

Using the same model as the static analysis, all natural frequencies were found to be larger than 33 Hz; therefore, the static analysis is permissible. The maximum stress of 58,289 psi was found in the frame foot

' bolts by absolutely summing the stresses from each of the three seismic load components together with normal operating and nozzle loads. This stress is less than the ASME code allowable of 61,500 psi.

In addition, the computed maximum deflection of 0.0068 in. is less than the maximum allowable to assure functional operability (0.025 in.).

1 During the review of the field installation it was noted that the motor / pump coupling was not installed. However, this concern was adequately resolved by an LP&L letter, W3S82-1262, dated August 31, 1982, which indicated a completion date of October 24, 1982 for the coupling installation. Durf ng the review of the qualification report it was not evident that the application of Load Cases 4 and 5 was conservative. Also, it was not evident that the load cases used to calculate bolting stresses were conservative.

Based on our observation of the field installation, review of the qualification report, and the clarifications provided by the applicant, it is concluded that the pump is adequately qualified for the prescribed loads pending resolution of the conservatism concerns identified in the previous paragraph.

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BORIC ACID TANK CIRCUI.ATING VALVE (NSSS-2) l The boric acid tank circulating valve, supplied by Fisher controls, t

with Orawing No. 50A9828, Revision E is welded in the chemical.and volume i

control piping system at the minus 35 ft elevation of the reactor auxiliary I

building. The reference document for the valve's qualification is the Fisher Controls report, Seismic Analysis for Order 1-46610, dated April 3, l

1976.

The valve was qualified by static analysis using a Fisher "in-house" l

computer code based on Tisher's Engineering Standard ES100. Revision B, dated April 8, 1975. This code basically uses beam assumptions in the static analysis and natural frequency calculations. The valve was analyzed for 3 g accelerations in each direction with the resulting responses combined by SRSS summation. The natural frequency calculation indicated a fundamental frequency of 26 Hz which is above the ZPA frequency for the Waterford Site. Therefore, the static analysis is permissible. The analysis indicated a maximum stress of 21,919 psi in the yoke legs; this value is less than the ASME code allowable of 36,000 psi. Deflections were also computed; however, no allowable value was given.

During the inspection of the field installation it was noted that the leak line supports had not been installed. This concern was adequately resolved by an Ebasco letter (Wills to DeBruin) dated Septemoer 1,1982, which indicated completion by September 3,1982, for the installation.

During the review of the qualification report it was noted that no allowable value for the computed deflections had been given.

In addition, there was no indication that Fisher's "in-house" computer code, used in the

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analysis, had been verified.

Based on our observation of the field installation, review of the qualification report, and the clarifications provided by the applicant, it

j is concluded that the valve is adequately qualified for the prescribed loads pending resolution of the deflection and computer code verification concerns identified in the previous paragraph.

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BORIC ACID PUMP DISCHARGE VALVE (NSSS-3)

The boric acid pump discharge valve (Orawing No. 039963, Revision H),

supplied by the William Powell Company, is welded in the chemical and volume control piping at the minus 35 ft elevation of the reactor aux 11tary J

- building. The reference document for its qualification is the William Powell Company report entitled Report on Analysis of Valve for Seismic Conditions, dated June 1, 1972.

The valve was qualifted by static hand beam analysis with 3 g seismic loads applied perpendicular to the weakest bending axis. Normal operating l

and thrust loads were also applied. A single lumped mass natural frequency

'f calculation indicated that the lowest frequency was 51 Hz and thus a static

'i analysis was justified. Under the applied loads the maximum stress of 14,360 psi was found in the body to bonnet bolting. This value is less than the ASME code allowable of 32,000 psi. Computed deflections (0.006 in.) were also within manufacturing tolerances.

During the field inspection of the valve it was noted that class IE heat tracing wire had been routed through pipe supports and that i

installation of the heater cable to the valve was not complete. The concern that the heat tracing wire may be clipped in the pipe support l

during a seismic event was adequately resolved by issuance of a design change notice (No. 426, RS), which specified that'the wire be routed remote from.tructural elements in pipe supports. The concern that the heater cable was not installed was also adequately resolved by an LP&L Letter, W3582-1262, dated August 31, 1982. This letter specifies a completion date of October 24, 1982 for the heater cable installation.

I Based on our observation of the field installation, review uf the qualification report, and the clarifications provided by the applicant it is concluded that the valve is adequately qualified for the prescribed loads.

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HOLDUP TANK C (NSSS-4) j l

The holdup tank was reviewed diaring the first audit. A major l

discrepancy was found between the f.upport configuration analyzed and that j

installed in the field.

It was chosen for the second audit to allow a i

thorough follow-up of the corrective action. The qualification details for i

this item are discussed in the first audit's report.

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FEEDWATER CONTROL VALVE (NSSS-5)

The feedwater control valve (Model No. 51A6372, Revision G) was supplied by Fisher Controls. The valve is weld'ed into feedwater piping at the 46 ft elevation of the reactor Auxiliary building. The qualification report, Seismic Certification for Order 1-51008, Serial No. 5900961,datS May 4,1976, was supplied by Fisher Controls.

Qualification was with an equivalent static analysis based on a computer code implementing the calculations in Fisher Engineering Standard ES-100. The static analysis was justified by a fundamental natural frequency calculated to be 22.5 Hz. This is well above the 5 Hz zero period acceleration frequency of the mounting location. Seismic stresses w3re calculated as an SRSS combination of the stresses for a 3 g load applied in each direction independently. The maximum stress of 29,400 psi occurred in the yoke legs. This is less than the allowable of 36,000 psi.

Review of the qualification report showed that the computer program was not verified. This will be done for the review of the boric acid tank circulating valve (NSSS-2). The review also showed that a positioner mounted on the valve in the field was not included in the analysis.

Further inv'estigation showed that the positioner had no safety function.

During the field inspection, the sister valve to this valve was observed to have an electrical cable attachment which could be tensioned under thermal motion in the appropriate direction. The thermal analysis for the associated piping predicted thermal motion that would not place the cable in tension, so that lack of slack in the cable is acceptable.

During the field inspection, the air lines to the valve appeared to be inadequately supported. Supports for the air lines had been designed but not installed.

Installation is guaranteed by field change request No. FCR-IC-P-451. These air lines were also detached from the valve. This had been done so that the valve could be isolated from a pneumatic system integrity check. The procedure for the check, Mercury Procedure M123-72A, requires that the air lines be re-attached after the check.

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Based on our observation of tha field installation, review of the qualification document and clarifications provided by the applicant, the feedwater control valve is qualified for seismic loads, pending the verification of the computer code described above.

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RESISTOR INPUT CARD (NSSS-6)

The resistor input card, supplied by Westinghouse, with Model No. 2837A86601, is mounted with standard card mounting hardware in the process instrument rack at the 46 ft elevation of the reactor auxiltapy building. The reference document for the device's qualification is the Westinghouse report, Seismic Operability Demenstration Testing of the l

Westinghouse ISD 7300 Series Process Instrumentation Bistables, WCAP-8828, dated December 1976.

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.i The resistor input card was qualified by multifrequency sine beat and multiaxis testing. Multifrequency excitation was achieved by superposition of various sine beats and multiaxis response was obtained by four rotations of the equipment in each test. The device was qualified to an in-cabinet response spectra that was developed from a generic floor response spectra.

The generic floor spectra enveloped the Waterford site specific spectra for the mounting location. No natural frequencies were determined for this device. Five 08E and four SSE tests were performed with the card mounted in the PC card frame, which was attached to a rigid fixture on the test table. Functional operability was claimed to be demonstrated during the test; however, there was no data to support this conclusion in the qualification report.

During the review of the field installation it was noted that several rather long cables (3 ft) had not been secured. This concern was e

adequately addressed by review of the installation procedures _and the I

issuance of an Ebasco letter, Wills to DeBruin dated September 2,1982.

This letter indicated that the wire bundles will be secured by October 30, 1982. As previously noted, during the review of the qualification report j

there was no evidence supporting the conclusion that functional operability was verified. Therefore, the applicant was requested to provide data to support this conclusion.

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l qualification report, and the clarifications provided by the applicant, it 1

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4 is concluded that the resistor input card is adequately qualified for the aj prescribed loads pending resolution of the concern identified in the ii previous paragraph.

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INDICATOR (NSSS-7)

The indicator (Model No.1151, Serial No. 0200, Tag No. PI-1018) was supplied by Sigma. Purchase Order Specifications are contained in CENPO Specification No. 9270-ICE-0005. Revision 01 which also refers to Engineering Specification for Instrument and Control Equioment, Specification No. 00000-ICE-0005. There are a total of 26 indicators.

I Each measures 6.05 x 2.28 x 5.87 in. and weighs about 25 oz. The item inspectad in the field was mounted on panel CP7, which was located in the control area of the auxiliary building at the 46 ft elevation. The i

mounting on the panel consisted of standard mounting hardware. Seismic qualification is done through tests performed by Environmental Testing Corporation and documented in Report No. 13906, titled Report of Test en Environmental and Seismic Qualification of Various Items for Combustion Engineering Under Purchase Order No. 9870612.

The dynamic tests were performed with a mounting which simulated the inservice. condition. Thesa were biaxial tests with random, independent inputs. Each had a minimum duration of 30 seconds. Each test was repeated in two positions with inphase and out-of phase inputs. There were a total of five 08E level tests followed by an SSE level test. A test response spectrum (TRS) was generated in each case. These tests were performed to generic spectra, but in every case the equipment RRS is enveloped by the i

TRSs generated.

The tests performed are adequate. However, the Purchase Order Specification requires the followinc:

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Scale range 15 to 25 (x100) (psia) linear 2.

Accuracy 1.5%

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Screw terminals 4.

Measures pressurizer pressure, i

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and it was accepted in spite-of performance with an accuracy of 5%.

Based on our observation of the field installation, review of the qualification docu.nent, and the applicant's response to our questions, the indicator is adequately qualfied for seismic environment pending resolution of the accuracy issue.

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RESISTANCETEMPERATUREDETECTOR(NSSS-8) l The resistance temperature detector (RTO), Model No.104AFC-1, was

j supplied by Rosemount. It is welded to primary coolant pump iniet piping at the 15 ft elevation of the containment building. The qualification report, Seismic Vibration Report on a Temperature Sensor for Combustion

Engineering Co., No. 27320A, dated July 22, 1975, was supplied by Rosemount.

A single frequency, multiaxis test qualified the RTD.

Fundamental natural frequencies of 20 Hz in both transverse directions justified the single frequency test, since the zero period acceleration frequency throughout the plant is 5 Hz or less. No resonance survey was conducted for the axial direction on the RTD. This is acceptable because of the inuch greater stiffness th this direction. The test mounting accurately reflected field mounting conditions. Sine dwell tests of 2 g in each transverse direction were performed at the fundamental and at 25, 33, and 44 Hz. This is well beyond the requirement of 0.3 g in the transverse and 0.25 g in the axial direction.

Based on our observation of the field installation, review of the qualification document and the applicant's response to questions, the resistance temperature detector is adequate for seismic loading.

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RCP S GNAL PROCESSOR (NSSS-9) 1 The RCP signal processor, supplied by Bently-Nevada, with Model i

No. 18740-01, is mounted with two 10-32 and four 1/4 in, bolts in the plant protection system cabinet at the 46'ft elevation of the reactor auxiliary building. The reference document for its qualification is the Wyle Lab -

i report, Seismic Simulation Qualification Test Report on a RCP SSSS l

, Signal processor, Model 18740-01, dated June 15, 1978, with Report No. 43844-1.

f' The device was qualified by rsndom multifrequency (with superimposed sine bursts), multtaxis testing. The device was mounted with six 10-32 bolts in the laboratory testing. Sine sweep resonance searches revealed natural frequencies of 18 Hz in the side-to-side, 18 Hz in the front-to-back, and 28 Hz in the vertical direction. The processor was qualified to a generic spectra which envelopes the Waterford site specific spectra at the mounting location. In addition, the test response spectra enveloped the required response spectra at all frequencies. Some environmental qualification was done in sequence with the seismic testing.

I 42 08E and eight SSE tests were performed and functional operability was monitored in each test.

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During the inspection of the field installation it was noted tnat loose cables in the cabinct had n;i been secured. This concern was adequately resolved by the review of the installation procedures and the issuance of an Ebasco letter, Wills to DeBruin dated September 2, 1982, which indicated the wire bundles will be secured by October 30, 1982.

ll During the review of the qualification report it was noted that there was an equipment anomoly during the humidity and temperature environmental I

testing. This anomaly was later shown to be inconsequential. After l

several of the qualification tests, a cracked electrical connector was i

discovered. This concern was adequately resolved by noting the

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conservatism in the generic spectra and by the indication that this cracked connector did not affect the equipment's operation in subsequent SSE tests.

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Based on our observation of the field installation, review of the qualification report, and the clarifications provide by the applicant, it is concluded that the RCP signal processor is adequately qualified for the prescribed loads.

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10. REACTOR TRIP SWITCHGEAR CABINET (NSSS-10)

The reactor trip switchgear cabinet (no model number) was supplied by Unit Electric Controls, Inc. It is located at the 21 ft elevation of the reactor auxiliary building. The qualification report, Seismic Simulation

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Test program on Reactor Trip Switchaear, No. 42835-1, Revision A, dated -

January 13, 1975, was provided by Wyle Labs.

A multifrequency, multiaxis test progi-am qualified the cabinet.

Resonance testing showed fundamental natural frequencies of 14.5 Hz in the j

side to side and 12.5 in the vertical direction, all above the zero period I

acceleration frequency for the mounting location of 4.4 Hz.

i The TRSs enveloped the RRS everywhere except below 2.a Hz. This caused no concern for the cabinet, because its fundamental natural frequencies are all well above 2.4 Hz. There was concern that the lack of i

envelopment could affect the conclusion that operability was demonstrated for the cabinet mounted relays. However, since these devices are designed to operate very rapidly to prevent arcing. damage, their individual components are very compact and strong. In addition, the breaker mechanism l

is loaded by a strong spring in the normal operating position, which would

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l prevent low frequency motion associated with clearances in the mechanism.

Therefore it is unlikely that the breakers would, have a natural frequency under 2.4 Hz.

L During the testing, one of the circuit breakers failed to close. This raised a concern about using the circuit breaker in an application where it must close to perform a safety function. The failure of the circuit breaker to reclose occurred in one of the nine breakers tasted.

Examination of the subject breaker showed it to be defective with misaligned linkages. Since this anomaly was noted in the first attempt to I

reclose the breaker, it is judged that this was a random failure attributable to manufacturing. All of the other eight breakers functioned

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(including reclosure) without incident.

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The test installation used high strength bolting. This raised a concern, since the field bolting was not clearly high strength. The concern was addressed by noting that the testing was perfarned at levels sufficiently above those required to ensure that any reasonable bolting l

, material would be adequate for the field installation. The ratio of applied versus required acceleration level at the fundamental natural frequency (S-5 and F-B) of the cabinet is 25. Applying this to the yield strength of the bolting material gives a field bolting required yield strength of 6.6 ksi. Any reasonable bolting material would meet this requirement.

Based on our observation of the field installation, review of the qualification document, and the applicant's responses to questions, the reactor trip switchgear cabinet is adequate for seismic loads.

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11. RECORDER (NSSS-11) i 1-4 i

The recorder, supplied by Westinghouse, with Model No. 75RE201/101-000/2212, is mounted in the nuclear instrument panel with j

l standard mounting hardware and a rear bracket. The panel is located at the j

46 ft elevation of the reactor auxiliary building. The reference document i

for the device's qualification is a Westinghouse Advanced Energy Systems Division report, Seismic Test of Westinghouse CID Panel Mounted Process i

Instrumentation, dated February 1981, with Report No. EL1348.

The recorder was qualified by random multifrequency, multiaxis testing. Multiaxial testing was achieved by four rotations of the specimen in each test. The equipment mounting during the tests was identical to the field mounting. Resonance searches revealed no natural frequencies less than 50 Hz from the 12 accelerometers used. Aging of the equipment at 50*C for 500 days was done prior to seismic testing.

Five OBE and four SSE tests were performed with functional operability monitored during the testing. A shift of less than 2% in the pen readings was observed.

During the inspection of the field installation several questionable field construction practices were observed. First it was noted that the rear bracket relied on friction (bolt preload) to maintain the vertical support of the recorder. This concern was adequately resolved by a design change notice NY-IC-303 R2 which modified the bracket design.

In addition, this particular mounting appeared to be an isolated instance necessitated by installation space limitations. Another item noted was that some cable tiedowns were mounted to painted surfaces with adhesive glue. A concern about the life of the glue was adequately addressed by a field change i

request FCRE-1900, which specified that these tiedowns also be secured with screws or bolts. During the field inspection it was noted that loose cables had not been secured. As with other cabinets, this concern was l

resolved by inspection of two installation procedures and the Ebasco letter, Wills to De8 ruin, dated September 2, 1982.

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.,,........_...:.....-..........-....-.--_...:...-.u.r.u.-

.a

.....u.

d

.I ll Based on our observation of the field installation, review of the qualification report, and the clarification provided by the applicant, it is concluded that the recorder is adequately qualified for the prescribed loads.

i

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. c._ __u 2

_ _. 2 2._,..

a_,

u,

./

12. CEDM REED SWITCH POSITION TRANSMITTER (NSSS-12)

The CEDM reed switch position transmitter (150 in. type) was supplied i

l by Combustion Engineering.

It is mounted on the CECM on the reactor vessel head. The qualification report, Seismic Qualification Testina,150 In.

Reed Switch Position Transmf +.ter and Bendix Electrical Connector, No. TR-ESE-149, dated February 2, 1977, was supplied by Combustion Engineering.

A biaxial, mult1 frequency test was performed to qualify the switch.

However, the reed switch was tested in only one position, so that the test results are not conclusive. Comoustion Engineerir.g had caught this oversight in qualifying the switch for other plants, and performed testing to correct the deficiency. A report of the testing will be forwarded to be reviewed for qualification of the switch.

l l

Based on our review of the field installation, review of the qualification documents, and the applicant's responses to questions, the CEDM reed switch position transmitter is adequate for seismic loading, pending resolution of the open item identified above.

i t l

20

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=u.

w,w

. -.- p --..

13. PRESSURE TRANSMITTER (NSSS-13)

,j The pressure transmitter (Model No.1153GA9, Tag No. PT1010) was supplied by Rosemount. The purchase order specified Rosemount Model 1152GP or equal-The one in the field was 1153GA9, which is reportedly better.

This locally mounted item is placed in the reactor building at an elevation of 21 ft.

It weigits about 21 lb. The mounting consists of horizontal and vertical plates, with the plate being bolted to the strut using four 5/16 in. bolts. The appurtenances were loose and flexible and would not affect the dynamics of the system. This item was qualified by test. The tests are documented in RMT Report 3788: Qualification of Test Report for Rosemount Transmitters, Model 1153, Series A, dated March 28, 1978.

Dayton f. Brown Laboratories prepared the report for Rosemount. CE reviewed and accepted the report according to the acceptance letter RAR No. 9403340-26.

The dynamic qualification consisted of type testing. The medal tested was 11530A5.

It is representative of all 1153 Series A transmitte s.

The remainder of the model line differs by the spring constant (thickness) of the sensing diaphragm. The stiffness of the metal se'ising diaphragm, whose movement is minute (0.004 in.), does not constitute a significant design difference. The tests were conducted at Environ Laboratories, Inc. in Minneapolis, Minnesota. The sine-sweep test did not indicate any natural frequencies in any of the vertical, side-to-side, or front-to-back directions below 40 Hz. This was followed by sine-dwell tests at 10, 20, and 30 Hz with an input of to 3.5 g's.

The comparabh, required g-levels are 0.25 g in each direction.

The equipment converts pressure to electrical signal. The single frequency, single axis tests are adequate for this relatively rigid item.

All units performed well during the testing, exhibiting t0.1% deviation from readings taken prior to the test.

Following the test, all readings were within the acceptance level of 0.5% of span with the exception of zero reading for transmitter Serial No. 106186, which deviated by 2*;.

However, this was a one item occurrence which corrected itself with the passage of time. Hence, it is of no consequence.

l l

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- Amus

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Based upon the field observation and the review of the qualification j

report, the pressure transmitter is adequately qualified for the seismic f

t environment.

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14. 20 KVA INVERTER (80P-1)

I j

The 20 kVA Inverter (Model No. SV1200/AC34R/TS200MB/RL14, Tag No. SUPS 3MB-S) was supplied by Solid State Controls, Inc. The Purchase Order Specification 215-70 contains'the general specification, while

~

details are in Project Identification No. LOU-1564.282. The rectangular box type structure measures about 111 W x 89 H x 36 0 in. and weighs about 4,500 lb. Two of these were located side by side in the auxiliary building at the 21 ft elevation.

It is a part of the vital AC system and supplies emergency 120 V power. The mounting consisted of seven 1/2 in, bolts attached to the floor. There were eight bolt holes in the base; however, due to inaccessibility, there were only seven bolts installed in the field. An analysis was done which showed the strength adequacy for this mounting. The referenced qualification document was: Summary Report on Seismic Evaluation of 20 kVA Inverter to Solid State Controls, Inc., dated November 23, 1977.

It was prepared by Battelle Columbus Labs for Solid State Controls, Inc. and reviewed by Ebasco.

This equipment was qualified through test. The laboratory mounting had six 1/2 in. bolts. The dynamic test consisted of single axis random input with cross coupling accounted for by increasing the input level based on preliminary test and analysis. This was achieved through initial testing and calculating the coupling effect based on off-axis response.

TRSs were generated for each test. There were 15 OBE and three SSE level tests performed. In each case the TRS enveloped the RRS adequately.

Operability was verffted.

There were some in situ tests performed on this unit by Wyle Laboratories. The results of these test are reported in the document:

Seismic Racertification Analysis and Test of Class IE Static Uninterruotible Power Supply, Test Report No. 46097-1, dated May 1982.

These tests were performed to support the analysis. The relevant results are:

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1

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In Situ Test Analysis (Hz)

(Hz) i i

,i s/s 16.8 15.1 i

f/b

'23.5 22.1 i

Coupled s/s & f/b 25.1 25.7 l.

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The correlation appears very satisfactory. The critical stresses from the analysis are u follcws:

Allowable Stresses (AISC)

Total Stress 1

Identification (psi)

(psi)

-)

Anchor bolts (ASTM A307) 9,948 (ter.sion) 19,736 i

5,165 (shear) 10,000 Structural member 11,667 21,600 The stresses are within the allowables.

The tests performed are adequate. Operability was verified. However, during the field inspection, two things were detected:

1.

The first concerned the pl' ate box on the top of the unit which

)

was not securely attached.

This problem was corrected and confirmed after it was pointed out.

l, a

2.

The second problem is related to

's two cabinets not being

^

.I connected on their common side. The qualification test report had recommended that this be done with a spacer grid in-between.

1 On inquiry, the applicant indicated that there was difficulty in

[

procuring the parts and this would be done as soon they became ll a

0 available.

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k Based upon our obsenvation of the field installation, review of the qualification reports and the response to our questions, the 20 kVA inverter unit is adequately qualified for the seismic environment, pending confirmation of the correction of the mounting deficiency, as indicated.

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15. DIESEL GENERATOR LUBE OIL PIPING (80P-2)

.I I

The diesel generator lube oil piping was supplied as part of the 1-generator (Model No. KSV-16-T) by Cooper Energy Services (formerly j

4 Cooper-Bessemer). The piping is located adjace'nt to the engine at the j

f t

j 21 ft elevation of the reactor auxiliary building. The qualification l:

~

report, Emergency Ofesel Generator, Engine Mounted System, AM-3383, CES-0279-1, dated July 27, 1976, was supplied by Cooper Energy Services.

The report presented a dynamic analysis. However, tne number of dynamic degrees of freedom included in the analysis was not clearly adequate. Therefore the piping was qualified by an equivalent static analysis, as allowed by C.1 of Regulatory Guide 1.100. This was done using the 1 g static solutions in all three directions presented on pages A-80 through A-194 of the qualification report. Stresses for each direction were multiplied by the product of the pertinent peak spectral value and 1.5.

The maximum of the SRSS combination of these stresses in all three directions was 14,000 psi, well under the 27,000 pst allowable. Because of this margin, the analysis was accepted despite the fact that three short j.

runs of pipe were not included in the model. Lack of consideration of the l

I 100 psi pressure loading was accepted on the same basis. The support i

configuration of the model matched field mounting conditions.

Based on our observation of the field installation, review of the qualification document, and responses by the applicant to questions asked, the diesel generator lube oil piping is adequate for seismic loading.

I 26

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x-

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=.: -.

=.

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16. LEVEL SWITCH (BOP-3) l l

The level switch, supplied by Magnetrol, with Model No. A103F-TOM-EP/VP-51M04-SIM04, is mounted with eight 5/8 in. bolts on the top of the jacket water standpipe located at the 21 ft elevation of the reactor auxiliary. building. The reference document for its qualification' 4

is a Wyle Labs report, Liquid Levels Controls, dated May 2',1977, with Report No. 43235-1.

i The switch was qualified by random multifrequency, multiaxis testing.

Prior to qualification testing, 0.2 g sine sweep resonant searches revealed natural frequencies of 45 Hz in the side-to-side,17 Hz in the front-to-back, and 32 hz in the vertical direction. The qualification testing was done for Model A153F, which is nearly identical to A103F. The seismic qualification testing was done in sequence with environmental testing and aging. Five OBE and one SSE seismic tests were performed with the test mounting identical to the field mounting. Functional operability was monitored during and after the tests with some chatter cbserved during the tests.

l l

Dur.ing the field inspection, it was noted that the unit was free to l

rotate one quarter turn. Also, a 5 ft length of flexible electrical conduit leading to the switch was unsupp'orted. The rotation concern was adequately resolved by LP&L securing the unit on September 2,1982. The concern about the unsupported conduit was resolved by noting that the conduit was remote from other equipment and that the conduit is designed to relieve the loading on the electrical leads. As previously indicated, the I

qualification report indicated chattering during the seismic 1

qualification. This concern was also resolved by contacting the equfpment vendor who indicated that the switch was not required to function during the seismic event.

Based on our observation of the field installation, review of the qualification report and the clarifications provided by the applicant, it is concluded that the level switch is adequately qualified for the prescribed loads.

27

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m,

.a

17. AXIAL FAN (BOP-4)

)

The axial fan [Model No. Ed-26-870(S-41), Tag No. E28(3A-SA)] was supplied by Joy Manufacturing (ompany. The Purchase Order No. is NY-403548, dated April 23, 1976. Other rsleyant information is contained in Ebasco's l

Specification 602-75 and Project Specification No. LOU-1564.748L. This -

I i

enclosed direct motor drive fan is 84 in. in diameter and 48 in. long.

It weighs 4,048 lb. The unit is located in the auxiliary reactor building at an elevation of 56 ft, 6 in. The field mounting consists of members welded to the fan housing which are bolted to a vertical wall. 'Each extension attachment has four 5/8 in. bolts. This fan is part of the diesel generator room 'A' ventilation system.

It evacuates the diesel generator room and maintains the temperature within a limit.

It operates at 870 rpm and has a 60 hp motor. The qualification document referred is: Axial Flow 4

Fan [E-28(3A-5A)] S-41, dated September 28, 1976. It was prepared by Joy Manufacturing Company and reviewed by Ebasco.

The unit has been qualified by analysis. The lowest shaft frequency is around 41.5 Hz indicating a relatively rigid unit. This justifies the static equivalent analysis performed. The required acceleration levels in this range are 0.49 g in each of the horizontal and 0.3 g in the vertical direction. The critical parameters to be checked for seismic events are:

1.

The clearance between the tips of the fan and the stationary l

housing 2.

The clearance between the motor rotor and stator l

3.

Maximum stresses.

l These are calculated and compared as follows:

Total Stress Allowable Stress Identification (osi)

(psi)

Anchor bolt 26,046 33,000

[

t Shaft 5,122 45,000 28

. ~

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.mx_-- mw

v. c-

.., e. --

E Critical Deflection Allowable Deflection Identification (in.)

(in.)

~3

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Fan rotor 2.622 x 10 0.16

-5 Motor rotor 7 x 10 0.025 The analysis is adequate. The critical stresses and deflections are within allowables. However, balancing of the unit installed in the field has not been performed.

.l Based on our observation of the field installation and review of the qualification document the item is adequately qualified for seismic loads, pending confirmation of the balancing of the unit as installed.

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18. HVAC NATER PUMP (BOP-5)

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The HVAC water pump, Model No. 4013, is supplied by Buffalo Pumps Co.

l It is bolted to a concrete pad at the 46 ft elevation of the reactor

,I auxiliary building with six 7/8 in.' bolts. The qualification report, Model

1 4013 CRE pump, M2 Frame, dated January 1977, was suppited by Mcdonald

~

Engineering Analysis Co.

j.

ll; The pump was qualified.with an equivalent static analysis using the li computer code STRUDL. This was justified by a dynamic analysis which i;l predicted a fundamental natural frequency of 36 Hz. One g horizontal loads

't were included with a 0.67 g vertical load for each horizontal direction.

The envelope of these two load cases was considered along with nozzle and impeller loads. Load combinations were performed correctly. This was verified for nozzle load combinations by checking each calculation because the discussion in the report did not describe the treatment of nozzle i

loads. The treatment of the remaining loads was described adequately in the discussion.

1

~

The maximum stress, 9,956 psi, occurred in the impeller key. This was less than the 10,000 psi allowable. The maximum calculated deflection of 7 mils occurred between impeller and casing. This is less than the 8 mil maximum allowable deflection.

Based or. our observation of the field installation and review of the qualificattor document, it is concluded that the HVAC water pump is

<l adequately qualified for seismic loadings.

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19. GRAVITY DAMPER (BOP-6) y The gravity damper, supplied by American Warming & Ventilation Inc.,

j with Model No. DAA-P-2230, is mounted with 66 3/8 in. bolts in the I

containment fan cooler ducting at the 31 ft elevation of the reactor building. The reference document for its qualification is the American Warming and Ventilating report, Seismic Calculations of 0AA-P-2230 H.O.

Counter Balanced Damper with Sealed Jamb Construction, dated May 19, 1977.

The damper was qualified by static analysis using an "in-house" computer program. The documentation of the program indicated that the damper vanes are analy:ed as simply supported beams with distributed loads i

from seismic accelerations and pressure differentials. The damper was analyzed for 1 g horizontal and 0.67 g vertical accelerations with the resulting loads and stresses being combinea by SRSS summation. The maximum stress of 2,717 psi was found in tne vanes and compares to an allowable stress of 23,400 psi. The natural frequ.ancy calculation (based on a simply supported uniform beam) indicated the lowest natural frequency was 50 Hz and, therefore, the static analysis is permissible.

During the review of the qualification report it was noted that Section VII of the SQRT form was incorrect.

It was revised and incorporated into the audit package. Also, during the review of the qualification report it was noted that no bearing load allowables had been given and that no standard for computing the allowable stresses was mentioned. These i

concerns were addressed by closer examination of supporting literature supplied with the report.

From this information it was found that the maximum allowable bearing load was 1,810 lb and that the allowable stress was 90% of the minimum yield stress for the material. Since the actual bearing load is much less than 1,810 lb and because the allowable stress is consistent with the AISC code allowables, this concern was adequately resolve'd.

Based on our observation of the field installation, review of the qualification report, and the clarifications provided by the applicant, it l

is concluded that the gravity damper is adequately qualified for the

- j I

prescribed loads.

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20. THREE INCH 150 LB DIAPHRAM VALVE (80P-7) t l

The diaphram valve (Tag No. 7FS-V130, Model No. FS-302, S. No. 76-3527-8-14, Project Id. LOU-1564.103A, Purchase Order No. NY-403522 of December 31,1974)'was supplied by ITT Grinnell. This is i

a 3 in. non-nuclea: safety category 7, Seismic Class I, handwheel operatet!

diaphram valve with an ASTM-351 CF8 stainless steel body, an ASTM A-445 ductile iron bonnet, a Cr. MEPT Diaphram, and. an EPT "0" Ring valve. It is located in the fuel handling area at the 46 ft elevation. The i

qualification document is: Seismic Report W-146 Seismic Analysis for

'l Louisiana power & Light Company Order #NY 403522, Rev. 1, dated July 1979.

It was accepted by Ebasco Services Inc. according to the letter: LW3-1458-79 of July 25, 1979.

l The valve, located in the fuel pool system, functions as an isolator between the fuel pool and a component cooling water line.

It is welded to j

the piping. The report states that the valve was designed and analyzed in i

accordance with the 1971 ASME Boiler and Pressure Vessel Code, including j

winter 1973 Addendum. The natural frequency of the system is very high l

(1210 Hz). The system, thus, is relatively rigid and an equivalent static

(

analysis is adequate. The required acceleration levels for this location I

are 1.0 g in each of the horizontal directions and 0.67 g vertical. The (i

analysis was performed with 3.0 g's in each of the horizontal and 4.0 g's in the vertical direction. The resulting stresses in the components were well below their allowables.

i Considering the passive function of the valve, where the structural j

integrity alone would assure its adequacy, the static equivalent analysis is, adequate.

Based on our observation of the field installation, and the review of the qualification documents, the diaphram valve is adequately qualified for seismic loads.

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......_._.u.-.._.__.m I i.

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21. ONE INCH 2500 LB RELIEF VALVE (BOP-8)

The 1 in., 2,500 lb relief valve (ISI-25028) was supplied by the

1 Crosby Valve and Gage Co. The valve is welded to the safety injection piping at the 21 ft elevation of the reactor containment building. The

~

qualification report, 1 x 1 2,500 lb Relief Valve, No. EC-618, dated i-June 18, 1979, was supplied by Crosby Valve and Gage Company.

t An equivalent static analysis was used to qualify the valve. A hand f

calculated fundamental natural frequency of 374 Hz justified the static

'i analysis. One g loads in both horizontal directions and a 0.67 g vertical j

load were considered along with weight and operating loads. The I

calculation yielded a 3,500 psi maximum stress at the inlet neck, which

^

compares to a 16,500 psi allowable.

Operability of the valve during a seismic event was not addressed in the analysis. However, operability is assured by a feature of the design.

The valve stem connects to the seat via a ball / cup contact area. This prevents binding loads from developing between the upper and lower bearing surfaces by accommodating relative displacements and rotations between them.

The analysis did not include consideration of nozzle loads applied by the connecting piping. However, the connecting piping was seismically qualified, as documented in the Ebasco report, Stress Analysis Calculation No. 1020, dated April 17, 1981. Since the valve body is much stronger than the connecting piping, qualification of the piping justifies not considering the nozzle loads in the valve analysis. This conclusion is supported by the large margin of safety demonstrated above.

Based on our observation of the field installation, review of the qualification document, and the applicant's responses to questions, the I

1 in. 2,500 lb relief valve is qualified for seismic loading.

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22. HALF-INCH GLOBE VALVE (80P-9) l The half-inch globe valve (Tag No. 2HV-V621) was supplied by Velan l

Engineering Company. The valve is welded to HVAC piping at the 46 ft f

i elevation of the reactor containment building. The qualification report,

.t I

l j

Extension of Seismic Analysis to Manual Valves, SR-6684, Revision'1, dat%d j

December 10, 1981, is supplied by Velan Engineering Company.

l Qualification is by means of an equivalent static analysis, which was justified by a hand calculated fundamental natural frequency of 49 Hz. The l

valve actually qualified has an identical body to this valvi, but it has an actuator instead of a handwheel operator (see the Velan Engineering Report i

No. SR-6631). Extension of qualification to the handwheel operated valve is acceptable because of the high fundamental natural frequency of the t.

i actuated valve, and because of the reduced weight and eccentricity of the handwheel operated valve. The required seismic loads for a rigid valve at the mountirg location are a 0.5 g horizontal and a 0.3 g vertical load.

I g horitontal and 0.67 g vertical seismic loads in conjunction with weight.

and operating loads were considered in the analysis. Not considering a second horizontal seismic load was accepted because of the symmetry of the l

8 l,

valve. The method of combining loads was acceptable. The maximum stress l

in the valve body was 4,900 psi which is below the 26,200 psi allowable.

No deflection calculations were required since the valve need not operate l

during a seismic event.

i A small gap (1/8 in.) was noted between the valve and a nearby flange during field inspection. Hand calculations showed a maximum predicted i

seismic deflection of the valve of 1 mil. Therefore the possibility of contact between valve and flange is not a concern.

Based on our observation of the field installation, review of the

[

qualification document, and the applicant's response to questions, the

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half-inch globe valve is qualified for seismic loading.

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i 23.

INDICATOR (80P-10)

The indicator (Model No.1151, Tag No. EI GN 4613) was supplied by International Instruments. This panel-mounted device measures j

6.05 x 2.28 x 5.87 in. and weighs about 25 oz. The panels were located in the reactor auxiliary building at the 46 and 21 ft elevations. The mounting consisted of a fixture in the cabinet specifically designed for the indicator. The qualification of this ites is documented in Report No.

58I-3, Indicating Instrument Model 9270 and Meter Models 1122, 1136, and 1151, dated February 10, 1976.

It was prepared by Acton Laboratories for International Instruments and reviewed by Ebasco.

In the light of the more recent testing of the same equipment, as discussed in the section for Indicator (NSSS-7), the old test report only substantiated the general findings of the new tests. The qualification of this item is, therefore, based on the new test series and discussed in the section for the indicator identified above.

Based on the discussior: presented in the section for the Indicator (NSSS-7), this item is adequately qualified, assuming the satisfactory resolution of the concern discussed there.

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24. ELECTRIC RELAY (BOP-11)

The electric relay (Type NOR 137-8, Tag No. CX-610) was supplied by Reliance Electric Company. This particular item did not have a specific d

pu/ chase order and reportedly was art off the shelf item. This P&B relay l

was mounted on Cabinet 2A, Section E, with standard mounting hardware. The cabinet was located in the reactor auxiliary building at an elevation of 35 ft. The qualification document referred is: Seismic Simulation Test Program on Twenty One Components, No. 753.1, dated October 30, 1978. It was prepared by Wyle Laboratory (Test Report No. 44258-1, dated October 18, 1978) for Reliance Electric Company and reviewed by Ebasco.

l The relay was qualified through tests. The tests consisted of single frequency, biaxial (in each horizontal and vertical directions),

independent inputs (in pSase and out of phase) in the range of 1 through, 35 Hz with increments of one third octave. This amounts to a single frequency test. The ZPA level accelerations for the floor are 0.4 g.in each of the horizontal and 0.3 g in the vertical direction. The input ZPA level for the tests were 2.8 g's in each of the horizontal and 2.1 g's in the vertical direction. Out of the 21 specimens, 5 experienced contact chatter in the 5 to 35 Hz range.

~

i There are two resulting concerns from this test series:

a.

the use of the single frequency input for the test, and p

b.

chattering of the timers during the test.

The appitcant has been made aware of the inadequacy of using a single frequency input in tests on a generic basis and the applicant is committed to investigate and respond to the concern.

When asked about the chattering of the timers, the applicant product a letter from Ebasco Services Incorporated (dated August 10, 1979) to Mr. D. Harper of Reliance Electric Company addressing qualification of Electrical Comoonents. This letter states: "Ebasco has analyzed the 1

36 L

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circuits that the five relays are part of, and we have determined that j

contact chatter would in no manner compromise the safe operation or shutdown of the plant."

Based on our observation of the field installation, review of the qualification documents and particularly on the responses of the applicant to our question,. this unit is qualified for it's intended function, assuming a satisfactory resolution of the generic concern.

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25. FOUR INCH 300 LS GATE VALVE (BOP-12) i I

4 The gate valve (Model No. 4 in. 300 lb Gate Valve, w/ Actuator) was supplied by Anchor / Darling Valve Company. The valve, measuring lj 29 x 12 x 12 in., is located on the* condensate system piping in the reactor auxiliary building at the minus 4 ft elevation.

It is welded to the

~

i piping. The purchase order specifications are contained in Document No. NY-403458, dated October 31, 1973, Ebasco Specification 92-71 and Project No. LOU-1564.099A. The referenced qualification document is LAB No. 80.281: Seismic Class I Analysis of 3 and & In. Stainless-Steel Gate Valves with Handwheel Operators Waterford Steam Electric Station Unit 3.

S.J.O. Nos. 4463-64. -68, -69, -80

-99, -100.

It was prepared and reviewed by Anamet Laboratories, Inc. for Anchor / Darling Valve Company and accepted by Ebasco Services in the letter to Ms. Oori Solyan dated i

January 27, 1981.

i 1

The dynamic qualification of this valve is based on static analysis.

Analysis shows that the valve system is comparatively rigid, hence the static analysis. The loads considered were earthquake, gravity, piping and pressure. A load of 3 g was applied in each of the two horizontal and the vertical directions. This compares to a requirement of 1, 1, and 0.67 g.

This is a passive component in that it only has to maintain the pressure boundary in the condensate system. The stress analysis satisfies the criteria of faulted condition given in the ASME B&PV Code,Section III,

" Nuclear Power Plant Components," Subsection NC (Class 2) and ND (Class 3). The stress summary is as follows:

Total Stress Allowable Stress Location Identification (psi)

(osi) l i-Valve body Seismic + operating

+ internal pressure 11,531 37,a40 piping reaction

+

Yoke Seismic + operating internal pressure 4,980 18,480 1

+

+ piping reaction 38 1

. 7 * T77-E 7 * ' * * * " ' '

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The maximum deflection in the yoks of the valve was 0.0025 in. against an i

allowable of 0.020 in.

Based on our observation of the field installation and review of the

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qualification report, the valve is adequately qualified for seismic loads.

9 9

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