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Forwards Responses to Informal Questions Posed by 780804 NRC Memo on Seismic Qualifications.Submission Is Nonproprietary Version
	ML20147C600
Person / Time
Site:	Diablo Canyon
Issue date:	09/22/1978
From:	Crane P; PACIFIC GAS & ELECTRIC CO.
To:	Stolz J; Office of Nuclear Reactor Regulation
References
	NUDOCS 7810130058
	Download: ML20147C600 (64)
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Dear Mr. Stolz:

do Enclosed in support of our operating license applica-tion are responses to informal questions 1 through 10 transmitted to PGandE in an August 4, 1978 memorandum on the subject of seismic qualifications.

Because portions of the responses are Westinghouse propri-etary information, enclosed are 30 copies of the proprietary responses

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and 30 copics of the non-proprietary version of the same responses.

i Also enclosed are an application for Withholding Proprietary Infor-mation From Public Disclosure and supporting letters from Westing-house.

Five copies of these reports have been sent directly to Mr. Dennis Allison.

Kindly acknowledge receipt of the above material on the enclosed copy of this letter and return it to me in the enclosed addressed envelope.

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Very truly yours, Philip A. Crane, Jr.

Enclosures CC w/encs.:

Mr. Dennis Allison Service List w/non-proprietary enclosure

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1 NON-PROPRIETARY This package contains non-proprietary responses to informal questions 1 through 10 transmitted to PGandE in an August 4,1978 memorandum on the subject of Seismic Qualifications.

,f 00uestion 1 Seismic Qualification:

Auxiliary Safeguards Cabinet The Auxilia'ry Safeguards Cabinet contains relays that receive signals from the Solid State Protection System and upon actuation, close or open contacts that operate safe-

. guards devices, mostly valves.

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Information in regard to the electrical operability during seismic tests of the Auxiliary Safeguards Cabinet and associated relays has not been described in Section 10.3.2 of the FSAR amendment 50 or in Section 3.10 of the FSAR.

The Auxiliary Safeguards Cabinet may be structurally identical to the safeguard test cabinet; however, they are not electrically identical.

Provide information in regard to the electrical functions monitored during seismic shaking in order to demonstrate the seismic adequacy of the Auxiliary Safeguards Cabinet.

RESPONSE

1.

Auxiliary Safeguards Cabinet The Auxiliary Safeguards Cabinet contains rotary relays that are used to provide the same electrical function, i.e., safeguard actua-tion, as the relays contained in the output bay of the three-bay Solid State Protection System.

WCAP-3694 describes the seismic qualification of the rotary relays, and concludes that no contact j

bounce occurred and that the relays operated properly before, during and after the simulated seismic, event.

WCAP-8941 describes the seismic qualification of these rotary relays in the Auxiliary Safe-guards Cabinet, stating that the seismic levels tested in WCAP-8694 are 2 to 3 times greater than those req'uired for this. cabinet at the Diablo Canyon site.

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Instrument AC Inverter (Static Seismic Q)ualification:

00ESTI0fl 2 Inverter The static' inverters' function is to' supply uninterrupted The 118-volt, 60 Hz power to the vital AC instrument bus.

inverter operates from two power sources:

a DC voltage source or a 480 voit AC source.

In normal operation, the In the 480 volt AC source supplies power to the inverter.

event of an AC power f ailure, the DC voltage source sup-plies power to the inverter.

It appears from the information in the FSAR that the power source's to the inverter were not changed from the AC Provide source to the DC source during seismic shaking.

justif,ication that the tests performed demonstrate the seismic adequacy of the static inverter.

,. R_E_SP0ilSE

.The inverter is designed such that during normal operation, the inverter power is derived from the AC source with the DC source assuming the load _ ~ ~

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upon loss of AC voltage.

The only difference. in the system between the The bat-two(2), inputs is a diode, used primarily as a blocking' diode.

tory supply (normal DC source) is not in the Westinghouse scope of sup-j ply and was not tested as part of the system.

The diode (solid state)

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used is a'JEDEC device and is used in many military and industrial applications.

The military qualification requires that the device be subjected to G-levels much greater than required in this application and therefore the complete function of this one(1) diode was not tested.

However, the blocking capability was obsefved during the seismic test and its integrity was maintained throughout the testing and was there-fore acceptable.

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puring tric seismic test, a small DC power supply was used in place of the normal DC power source to verify the blocki'ng capability of the

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blocking diode, flad the diode shorted during the test, a protective device would have isolated the small DC power suuply, thus indicating

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flo such indications were observed.

Examination of the diode following the test indicated that no loss of integrity (open circuit) resulted.

Therefore, functional operability of the diode durin'g and after the test was demonstrated.

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QUEST 10114 Seismic Qualification:

Nuclear Instrumentation System The Nuclear Instrumentation System monitors the neutron flux level and provides reactor trip signals if certain power limits are exceeded.

a)

Only the power range channel was energized and moni-tored during seismic testing.

Therefore, it appears that the source range and intermediate range chan-nels, required for reactor start-up and shutdown protection, have not been seismically qualified.

Provide justification.

Section 7.5 of the FSAR indicates that the occur-rences of a seismic event does not render the source How-a'd intermediate range channels inoperative.

n ever, Section 3.10.2 of the FSAR (page 3.10-4) indicates that the source and intermediate range channels are not required to be seismically qualified since any design basis accident described in the FSAR can be terminated within acceptable limits by the power range channels.

Provide justification for this apparent inconsistency.

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~b)'- Section 3.10.2 of the FSAR (page 3,10-4) indicates that neutron detectors for the nuclear instrumenta-tion system power range channel are seismically However, the seismic information for qualified.

neutron detectors does not appear to be in WCAP-7821, WCAP-8021, or the seismic evaluation for postulated 7.5M Hosgri earthquake.

( Amendment 50 to 'the FSAR),

Provide the seismic qualification test information for neutron jatectors associated with the power range channel as well as those detectors associated with the source. and ' intermediate range channels.

c)

Westinghouse committed to. retesting an entire typical channel of the nuclear instrumentation system (including signal conditioning circuits and bistables) to verify that the bistables have the capability to change state during a se.ismic event.

Section 10.3.16.2 of the FSAR amendment 50 implies that only bistables have undergone additional testing versus an entire typical channel.

Justify the retesting of only the bistables, d)

Two tests were performed to demonstrate the func-tional operability of bistables as documented in WCAP-8831, Seismic operability demonstration testing of the Nuclear Instrumentation System Bistable Ampli-Tesf 1 (referenced as test 2 in WCAP-8831 fiers.

Section 5-15) indicates all bistables tripped as 4

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negative bistable was not tested during the seismic' shaking.

Test 2 (referenced as test 5 in WCAP-8831 l

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section 5-18) indicates 5 of 6 bistables operated as required during the test; however, it appears that the bistables were not tripped and therefore not The tested during the seismic shaking as ' required.

overpower-high range bistable experienced an

,j unexplained trip.

And the negative rate bistables was (again as in test 1) not tested.

Provide justi' fication that these two tests demonstrate the seismic l

adequacy of the Nuclear Instrumentation System.

RESPONSE _

'(a) as stated in FSAR 3.10.2, all design basis accidents discussed in

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I the FSAR can be terminated within acceptable limits by the power l

range channels.

T'he source and intermediate channels therefore do not require seismic qualification and have not been qualified.

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.Sh'utdown proced'ures will contain the fo'll'owing provisiins~in'Thi ~ ~

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event that the source range channels are rendered inoperative due to j

a seismic event:

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i (1) the operator will take appropriate action to preclude boron

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l dilution (2) prior to cooldown, boric acid will be added to the reactor coolant to ensure that the concentration is sufficient to maintain the reactor in a subcritical state.

l (b) The power range neutron detectors at Diablo Canyon are of the

-1 b,c integral mineral insulated ca.ble design, Model Number I

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type of design by the Westinghouse Electronic Tube Division.

The integral cable design was subjected to a vibration test with constant sinosoidal acceleration of 1g in the horizontal and vertical p' lanes. A constant sweep of 2.5 minutes duration was performed from 6 to 20 Hz in the horizontal plane.

Following this, another constant. sweep of 2.5 minutes duration was pe'rformed from 10 to 40 Hz in the vertical direction.

In addition, the design was subjected to a sinosoidal acceleratio'n of Ig amplitude for 20 seconds, in the horizontal plane, at frequencies of 6.5 and 7.4 Hz.

The performance of the detector was evaluated by checking the resis-f tance, capacMance, and neTitr'on serisittvity before-and-a'f ter the..__.. __ _ _ _ l test.

Also, a shock test was performed for this design.

The shock input provided a 0.15 second duration pulse which produced an acceleration

.with a 0.8g radial component 'and a 0.14g longitudinal component.

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The performance of the detector' was evaluated as before and no detectable damage was observed.

I The upper support for the, neutron detectors at Diablo Canyon is approximately at elevation 96 feet of the containment interior structure. The zero period acceleration at elevation 102ft. is approximately 0.7 's.

This value is less than the test accelera-9 tions achieved during the ihock and vibration tests discussed previously.

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Additional multifrequency and multiaxis test have been performed on 6,c a single NIS power range detectot (Model

) mounted in a sup-port assembly which simulated a lower bound or worst case detector holder.

The multifrequency inputs were developed in accordance with the guidelines set forth in'WCAP-8624 IEEE-344-1975.

The attached figure presents a comparison between the multifrequency and multi-axis test spectrum and the required Hosgri spectrum at elevation 102.0 feet of the containment interior.

As can be seen in the figure, the test spectrum envelopes the required spectrum.

During the test, the detector was energized from a hign voltage power supply, and an a-c signal was imposed on the high voltage electrode.

This a-c signal as well as 'd-c leakage currents were monitored on each of the two signal electrodes "to determine proper

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electrical operability.

At the completion of the seismic test, there was no observable,'

mechanical damage' and the electrical recordings revealed only a transient type electrical distrubance on one of the two signal electrodes.

This electrical disturbance was most likely generated by electrode displacement produced by the ' detector assembly impact-ing with the holder assembly.

The signal perturbations were small in amplitude (1,ess than 10-8 amperes) and would not cause any loss of protection capability of the NI System during normal operation in the presence of a normal detector signal (greater than 10-4 O

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e amperes) in an operating plant.

Subsequent detector acceptance tests performed by the detector manufacturer did not disclose any abnormal permanent change in the electrical or neutron sensitivity characteristics.

Thus it is concluded that the NIS Power Range Detector will operate as required during and after a seismic event'.

It is therefore concluded that this equipment is qualified for the Hosgri 7.5M event.

(c) The purpose of the demonstration test program was.to show electrical

& operability.

The electrical operability was. verified during Tests 2 (d) and 5 as described in WCAP-8830 for the high seismic OBE and SSE conditions respectively.

As a result of the test configuration-

. -.. - - -.... l (single rack in lieu of four) and the frame and rack damage incurred by the seismic test fixture malfunction; mechanical failures pre-vented the complete test run.

As indicated in Section 7 of WCAP-8830, the drawer securing method is being revised for high seismic plants and the de' tails were indicated in Westinghouse letter NS-CE-1609 dated 11/22/77.

' Test 2 performed a functional operability test of the bistables by introducing manually adjustable signal into the complete instrumen-tation channel as indicated in Figure 2-3 of WCAP-8830. The signal profile is shown in Figure 5-8.

The negative rate bistables was not exercised during this test; however, the signal conditioning equip-ment (same as that for positive rate bistable input) and six other bistables units with the same electrical and mechanical design performed as required.

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Recordings (Figures'5-12 through 5-16) fa'iled drawer latches.

indicate that five of the six bistable units performed their The only required function during the simulated seismic event.

bistable function not tested was the negative rete trip function.

Post seismic test electrical evaluation indicated that all electri-cal functions performed as required.

Further testing was not pos-sible because of the structural damage.

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Seismic Qualification:

Pressure and Differential Pressure QUESTION 5 Transmitters Pressure and Differential Pressure Transmitters sense the

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pressurizer level and pressure, and the steam generator feedwater/ system level, pressure, and flow.

The output from these transmitters are sent to the process control system equipment which generates the various reactor trips and safeguards actuation signals.

a)

PG&E's response dated October 3,1977 to an NRC Question Number 3.104 states that certain instruments are to be replaced, Steam Generator Narrow Range Level and Pressurizer Level.

Confirm that these instruments are in fact the Pressures and Differe,,-

Provide tial Pressure Transmitters being replaced.

the seismic qualification information for the j

replacement instruments, Steam Generator Narrow Range Level, Pressure Level, Reactor Coolant System Pres-sure, and Containment Sump Level.

b)

The electric test results for the transmitters, described in Section 10.3.17.2 of the FSAR Amendment, 50, demonstrated that the output oscillated around the normal signal level. These oscillations could causrtrips tiepending~on-the monitored._ variables _and... __ _.._

the trip point.

The tests do not demonstrate that the equipment is capable of meeting its performance specifications under service conditions (during seismic shaking).

Provide justification that the tests performed demonstrate the seismic adequacy of the transmitters.

.c)

The Fischer :nd Porter transmitter, No. 1302495 measures Steam Generator Level, was not tested, but

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was qualified by comparison to the Steam Generator Flow transmitter' No. 1082496, that was tested.

Justify the assumption, made on page 4-7 of WCAP-

'8021, Seismic Testing and Electrical and Control

. Equipment (PG&E plants), that the output of 1302495 would offset in a similar fashion under seismic excitation as 1082496.,

d)

The transmitter were only tested at some normal valve as indicated in Section 10.3.17.2 of the FSAR Amend-ment 50.

Define normal value and justify not testing over the full range of pressures, levels, or flows that these transmitters would be expected to operate.

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RESPONSE

(a) The following transmitters are being replaced at Diablo Canyon:

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b,c Steam Generator Narrow Range Level i

Pressurizer Level Reactor Coolant System Pressure Containment Sump Level The seismic tests of the pressure and differential pressure

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transmitters was performed using multifrequency triasial inputs

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guidelines for frequency content and phasing-set forth in WCAP-8624;

" General method of developing multifrequency biaxial test inputs for bistables."

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The transmitters were mounted to a test fixture in a manner which simulated actual field mounting.

A schematic of.the tr.iaxial test setup is shown in attached Figure 1_.

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QUESTION 3 Seismic Qualification:

Main Control Board Provide information in regard to the seismic qualification of individual Class 1E instruments and/or controls mounted on the Main Control board.

RESPONSE.

The qualifications of individual instruments and controls mounted on the Main Control board are contained in Paragraph 10.3.15.2 of the Hosgri Report.

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RESPONSE

5(b) Signal level oscillations associated.with seismic events were considered in the selection of system setpoints in order that i

the oscillations would not cause an invalid trip.

An amendment in Section 10.3.17.2 of the Hosgri Report is being prepared to clarify that issue.

RESPONSE

5(c) The Fisher and Porter transmitters No. 13D2495 (Narrow Range Steam Generator Level) are being replaced.

The Fisher and Porter transmitters No.13D2495 (Wide Range Steam Generator Level) are not safety related and do not require qualification.

1

RESPONSE

5(d) The meaning of normal value, as used in Section 10.3.17.2, refers to a transmitter output between the zero and full scale opera, ting range.

A transmitter tested for a seismic event at.any given level would be representative of all other levels on the scale as long as the value selected was not so close to either end of the scale that the transmitter would be constrained, preventing the mechanical system from floating freely during the seismic event.

.It should be noted that the effects of the seismic forces on the transmitter do not vary according to where the scale"is reading during a seismic event.

Any pressure transmitter converts pressure to forces.

It then measures these forces to determine the pressure.

The methods of measurement vary with design bu't force is always the quantity measured.

A seismic acceleration also imparts a force.

This force is a function of the mass of the device and its acceleration.

It will be added (or subtracted) from the other forces on the device and will thus provide a pressure deviation in the readout.

This force is not a function of the other forces on the device and is therefore not a function of the scale reading before is was applied.

There-fore, the deviation that it provides is not a function of the scale reading.

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RESPONSE

5(d) Continued At low pressures, the pressure forces can be small compared to the seismic forces and the relative deviation due to seismic forces will be larger than at.high pressures.

If, for example, the seismic forces caused a deviation equivalent to 5% of the total range of the device, the relative deviation when the reading was 5% of range would be 100% of reading.

If the read-ing was 90% of range, the relative deviation would be only 6%-

of reading. For this reason, all seismic errors are considered as a percentage of span, not reading.

Thus, determination of the seismic error is independent of the instrument reading.

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Control Acceler'ometer Posii.kn Y

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'(H2)

ControlAccelerheter Position 2

Run 13 6-5-78 s

270*

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,e QUESTION 10 Seismic Qualification:
Safeguards Test Cabinet Selected relays, switches, and components were continu-ously monitored during seismic testing as indicated in WCAP-8021, Supplement 1 Seismic Testing of Electrical and Control Equipment (Engineered Safeguards. test Cabinet for PG&E Plants)', May 1977.
Provide electric.a1 schematic diagrams of the test cabinet circuitry, describe the test set up, and identify the selected relays, switches, and components monitored during testing. Justify the seismic adequacy of relays, switches, and components that were not monitored during seismic testing.
RESPONSE
2 Figure 4 shows the electrical test setup for monitoring selected switches, relays, and resistor-light-diode combinations of the Safeguards Test Cabinet during its seismic test.
You will note that normally open_ and normally_ closed _ contacts _of_ switches..S804,..S807, S818 and S821 were mo'itored, as were normally open and normally closed contacts of relays K801, K804, K811, K821 and K822.
Two light-diode combinations, 058038 and DS8040 were.also monitored for continuity.
Component location is shown in Figure 5.
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Switches located in the top row (middle and side) and 3rd row (middle) were monitored. Relays located in the top row (side and middle), 2nd row (middle) and bottom row (side) were monitored.
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The switches, relays and resistor-light-diode combinations that were not monitored during the seismic tests are identical to the ones that were S.D
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t monitored, therefore are considered seismically adequate.
Note that the locations of the components monitored are in areas of expected highest 3
,,. i acceleration, i.e., middle of panel, top of panel.
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ML20147C600

Contents

Text

Dear Mr. Stolz:

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RESPONSE

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ML20147C600

Text

Dear Mr. Stolz:

RESPONSE

RESPONSE

RESPONSE

RESPONSE

RESPONSE

RESPONSE

_=.==v==._::_ E. a rsu.er-r =2 :1 a.=r.= r== ; =u = o.= = n=

=

.~=._

_=_ ::=..._

=

RESPONSE

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