ML17298A863

Forwards Info Requested in Sser 5 (NUREG-0857) Re Tests Performed for C-E on Load Limiting Devices in Reactor Vessel Lower Key Horizontal Supports

ML17298A863
Person / Time
Site:	Palo Verde
Issue date:	02/10/1984
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G Office of Nuclear Reactor Regulation
References
RTR-NUREG-0857, RTR-NUREG-857 ANPP-28836-WFQ, NUDOCS 8403020005
Download: ML17298A863 (19)

Text

REGULATORY FORMATION DISTRIBUTION S EM (RIDS)

ACCESSION NBR 0 8rt 0 FAAOIL'STN 50 528 STN 50 529 STN~50 530 AUTH SHAME VAN BRUNT<E"BE~

REC IP, NAME KNIGHTONgG ~

3020005 DOC ~ DATE: 84/02/10 NOTARIZED; YES Palo Verde Nuclear Stationi Unit ir Ar izona Publi Palo Verde Nuclear Stations Unit 2< Arizona Publi Palo Verde Nuclear Stationi Unit 3i Arizona Publi ALJTHOR AFFILIATION.

Arizona.Public Service Co, RECIPIENT AFFILIATION Licensing Branch 3

DOCKET- 0 05000528 05000529 OSOOOS30

SUBJECT:

Forwards-info requested in SSER 5

(NUREG 08S7),re< tests"

performed for C

E on load limiting devices in reactor--vessel low1er key horizontal supports, DISTRIBUTION CODE:

B001S COPIES RECEIVED:LTR L ENCL ]

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TITLE; Licensing Submittal:

PSAR/FSAR Amdts L Rel-ated Corr espondence NOTES:Standardized plant ~

Standardized plant; Standardized plant.

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Arizona Public Service Company P.O. 8OX 21666

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PHOENIX, ARIZONA 65036 February 10, 1984 ANPP-28836 WFQ/MSN Director of Nuclear Reactor Regulation Attention:

Mr. George Knighton, Chief Licensing Branch No.

3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3

Docket Nos.

STN-50-528/529/530 File:

84-056-026; G.l.01.10; D.4.02.1

Reference:

(A) NUREG-0857, Supplement No. 5, November, 1983.

Safety Evaluation Report.

(B) Combustion Engineering (C-E) letter, LD-81-069, to D.G. Eisenhut from A.E. Scherer, dated October 8, 1981.

Subject:

CESSAR-F Round 1 Question Responses.

(C) C-E letter, LD-83-105, to D.G. Eisenhut from A.E. Scherer, dated December 20, 1983.

Subject:

CESSAR-F Load Limiter Tests.

(D) Arizona Public Service (APS) letter, ANPP-28492-WFQ/KEJ, to G.W. Knighton from E.E.

Van Brunt, Jr.,

dated December 23, 1983.

Subject:

Schedule for completion of OL Review of PVNGS Unit 1.

Dear Mr. Knighton:

Attached is the information requested in Reference (A) regarding tests performed for Combustion Engineering (CE) on the load limiting devices in the reactor vessel lower key horizontal supports.

A telephone discussion was held December 21, 1983 between E.A. Licitra (NRC) and M.S. Nelson (APS) to clarify this request as follows:

(i)

Submit figure 3. 9.1-6b

[as stated in Reference (B)]: "Reactor Vessel Lower Key Load Limiter Requirements".

(ii) Submit a description of what testing was done and what the test results mean.

This information is provided in the Attachments to this letter.

S40S0a0005 8402ro PDR PDR

• DOCK 05000528

A

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Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3

Docket Nos. STN-50-528/529/530 Pile:

84-056-026; G.l.01.10; D.4.02.1 Page Two References (C) and (D) had provided updated schedules (first quarter of 1984 and February 29, 1984, respectively) for this submittal.

If you have any questions please contact me.

Very truly yours CV~ n~

E. E.

Van Brunt, Jr.

APS Vice" President, Nucl'ear ANPP Project Director EEVB/MSN:pt Attachments cc:

E. A. Licitra (w/a)

A. C. Gehr (w/a)

s

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STATE OF ARIZONA

)

february 10 1984

) as'NPP-28836 HFQ/MSN COUNTY OF MARICOPA)

/

I, Edwin E.

Van Brunt, Jr.,

represent that I am Vice President, Nuclear, of Arizona Public Service

Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.

s n ~a~

Edwin E.

Van Brunt, Jr.

Sworn to before ne this~ffe day of 1984.

Notary Public My. Commi'ssion Expires:

s My ConmIs;-ter B.",I,,"AprII 6, $ 9B7

~

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ATTACfBENT 1: Revision to FSAR Section 3.9.1.4.1 SEISMIC CATEGORY I NSSS ITEMS MECHANICAL SYSTEMS AND COMPONENTS 3.9.1.4 Consideration for the Evaluation of the Faulted Condition 3.9.1.4.1 Seismic Category I NSSS Items Analysis of the reactor coolant system components (reactor

vessel, steam generator, reactor coolant pump, pressurizer, and reactor coolant piping) and their supports have been performed in accordance with the methods described in CESSAR Section

3. 9.1. 4.1.

For each component and support

member, the calculated

loads, in combination with the seismic

loads, are below the loads specified for design and the stresses (pipe rupture in combination with SSE) are below those listed in CESSAR Table 3.9.3-2.

No components or supports of the reactor coolant system main loop for PVNGS were designed using the inelastic methods defined in Section III of the ASME Code as plastic instability or limit analysis methods.

The reactor vessel lower key horizontal supports include load limiting devices in accordance with 5.4.14.2(e) of CESSAR-F.

These load limiters are designed to remain elastic for all normal, upset and the SSE

loadings, and elastic system analysis is used to establish or confirm the loads specified for design of the components and supports for these conditions.

For loads resulting from postulated pipe

breaks, the load limiter devices are designed to deflect plastically, and nonlinear system analysis is used accordingly for proper calculation of the distribution of the loads among the system of supports.

Figure 3.9-1 (see page A-3) illustrates the performance requirements specified for the reactor vessel lower support key load limiters.

The dashed lines represent the stiffness and load ranges evaluated in the overall system analysis.

The test data points were within the envelope indicated by the solid lines.

The testing was performed on samples extracted from the heat specific material used in construction.

Twenty-one tests were run at various temperatures and at crush velocities representative of performance requirements.

The test results were within the specified load deflection limits.

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ATTACHMENT 2: Draft FSAR Figure 3.9-1 REACTOR VESSEL LOWER KEY LOAD LIMITER REQUIREMENTS AND TEST RESULTS A-2

1

REACTOR VESSEL LOWER KEY LOAD LIMITERREQUIREMENTS AND TEST RESULTS 27.78 KSI MAXIMUM 25.

ENVELOPE OF DATA 20.

10.

A~9.03 KSI MINIMUM 5.

E~180.67 KSI MINIMUM NO PERMANENT SET ALLOWED BELOW 5.0 KSI TEMPERATURE:200 F TO400 F

CRUSH VELOCITY:0 TO 21 IN/SEC MINIMUM STRAIN OA31 IN/IN~~

.2

.3 STRAIN (IN/IN)

ATTACHMENT 3 HONEYCOMB TEST DESCRIPTION A test program was performed to verify that the honeycomb material meets C-E's design requirements.

The design requirements are shown on Figure 1

and are summarized as follows:

1.

The honeycomb, will maintain a minimum stiffness of 8 x 10 kips/inch up to 180 kips without a permanent set.

2.

The honeycomb will crush within a load band of 325 kips to 1000 kips.

3.

The honeycomb will have a minimum deflection of 0.350 inches.

4.

The above three requirements apply over a

temperature range of 200'F to 400'F and a crush velocity range from 0 to 21 inches/second.

The, test program evaluated the effects of specimen

size, specimen temperature and crush velocity on the load-deflection characteristics of the material.

Twenty-one tests were performed and consisted of seven basic tests each performed three times.

Each stainless steel honeycomb specimen was taken from the same core block number (482-260) of honeycomb material as the production honeycomb for Arizona Nuclear Power Plant Palo Verde Units 1, 2 and 3.

All test specimens were precrushed identical to production pieces with the height of the specimens also the same as production pieces.

Specimens were connected to a backup plate to be consistent with production hardware.

The test program is defined in matrix form in Figure 2.

The laboratory tests were performed by National Technical Systems (NTS),

Structural Dynamics Laboratory.

The honeycomb samples were tested on the NTS Hiload Dynamic Test Frame.

The Test Frame is an electronically servo controlled hydraulic system.

The hydraulic actuator and load cell were each fitted with 6" x 10" x 1" steel plattens with integral cartridge heaters.

A temperature controller kept the plattens within + 5'F of the specific test temperature.

The servo command signal was generated by a

Hewlett-Packard 5451B Fourier Analyzer, which also acquired the load and deflection data.

Samples were preconditioned in a temperature controlled oven for a minimum of 60 minutes prior to test.

The oven was held within + 5'F of the specified temperature.

Ambient temperature was in the range of 70'o 90'F.

As samples were removed from the oven for testing they were placed immediately between the preheated plattens with a 5000 to 8000 pound preload.

Typical time from oven to plattens was 10-15

seconds, with the compression cycle following within 20 seconds.

1 Data was recalled from the HP 5451B disc drive and scaled.

Velocity was computed from the first derivative of the displacement time history.

Spectral components above a given cutoff frequency were cleared to minimize the high frequency noise inherent in the system.

The cutoff frequency for the static tests was 0.6 Hz; the cutoff frequency for all other tests was 150 Hz.

Test results are presented in C-E's FSAR change package for Reactor Vessel Lower Key Load Limiter Requirements.

The test results verify that the honeycomb material meets C-E's design load deflection requirements.

A-4

E S

HONEYCOMB DESIGN LOAD RE UIREHENTS Temperature:

200 F to 400 F

Crush Velocity:

0 to 21 inches/sec.

in the principle load direction 1000 Kips Haximum LOAD (Kips) 325 Kips Minimum K = 8 x 10 kips/inch minimum to 180 kips without a permanent set.

Hinimum Deflection 0.350 inches

.050

.100

.150

.200

.250

.300 DEFLECTION (Inches)

.350

.400 FIGURE 1

A-5

j I

HONEYCOMB TEST MATRIX TEST I

SAMPLE SIZE (inches) 3x 3x.813 SAMPLES 3-11 3-12 3-10 OVEN & PLATTEN*

TEMPERATURE oF 400 CRUSH VELOCITY (inches/second) 2 x 2 x.813 3 'x 2x.813 2-12 2-7 2-8 2-11 2-1 2-3 200 200 10 3 x 3 x.813 3-1 3-3 3-4 200 10 2x 2x.813 2-2 2-4 2-5 200 15 3 x 3 x.813 3-A 3-B 3-C 200 7**

3 x 3 x.813 3-14 3-15 3-D 200 10 Temperature Tolerance was + 5'F

+*

Repeat of Test 4

FIGURE 2

A-6

1

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