ML20147C884

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Submits Conformed Copies of Seismic Analysis & Confirmatory Info Re Subj Facil IAW 771107 Request.Believes Seismic Analysis Gives Assurance That Facil Can Be Oper Safely W/In Present Tech Specs
ML20147C884
Person / Time
Site: Plum Brook File:National Aeronautics and Space Administration icon.png
Issue date: 11/29/1977
From: Darmitzel R
GENERAL ELECTRIC CO.
To: Case E
Office of Nuclear Reactor Regulation
References
NUDOCS 7812180435
Download: ML20147C884 (42)
v • d • e


Text

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0E NUCLEAR ENERGY GENERAL ELECTRIC PROGRAMS DIVISION GENERAL ELECTRIC c O M P A N Y.

VALLECITOS NUCLEAR CENTER, PLEASANTON, C ALIFO R NI A 94566 PHONE: (415) 862 2211 TW X:

910 548 8481 November 29, 1977 l

Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C., 20555

Reference:

1) License R-33, Docket 50-73 2

Order to Show Cause, October 24, 1977 j

3 Letter, E. G. Case to R. W. Darmitzel, November 7, 1977

Dear Mr. Case:

General Electric hereby submits one signed and twenty (20) conformed copies of the seismic analysis and the confirmatory information on the General Electric NuclearTestReactor(NTR).

Submittal of the confirmatory information is in accordance with your request of November 7,1977 (Reference 3).

The seismic analysis is included as Attachment A and the confirmatory information is in-cluded as Attachment B to this letter.

General Electric believes that the seismic analysis (Attachment A) provides assurance that the NTR can be operated safely without endangering the health and safety of site personnel or the general public under the existing technical specifications which limit the reactivity held in control rods and experiments.

While completing the modifications as described in Attachment A and prior to approval of the seismic analysis by the NRC staff, General Electric requests to be allowed to continue to operate the NTR under existing procedures and commit-ments which limit the excess reactivity available for insertion as described in Items 1 and 2 of Attachment B.

Upon approval of the seismic analysis and com-pletion of the necessary structural modifications, these procedures and comit-ments would be discontinued and operation would be in accordance with the technical specifications..This approach assures safe operation of the NTR and will reduce the effort involving both General Electric and U.S. Nuclear Regulatory Comission personnel which would result from multiple temporary technical specification changes.

1 General Electric will be glad to meet with N.R.C. staff personnel at their con-venience to discuss the seismic analysis and/or other infonnation in the attachments.

E 7812,180Q3f THIS DOCUMENT CONTAINS POOR QUAUTY PAGES

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GENER AL @ ELECTRIC Mr. Edson G. Case Washingtcn, D. C.

In regards to Items 4 and 5 in Attachment B, General Elstric requests modification of the technical specifications for the NTR as shown in Item 5.

Sincerely.

/s/ R. W. Cannitzel R. W. Darmitzel, Manager Irradiation Processing Operation VCC Encl.

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4 G EN ER AL ()h ELECTRIC 4

AFFIRMATION 4

General Electric hereby submits the seismic analysis and confirmatory information on the General Electric Nuclear Test Reactor (NTR) requested by the Nuclear Regulatory Commission in their letter of November 7,1977.

4 To the best of my knowledge and belief, the information contained herein is accurate.

BY: /s/ R. W. Darmitzel j

R. W. Darmitzel, Manager Irradiation Processing Operation i

Submitted and sworn before me this day of 1977.

, Notary Public in and for the County of Alameda, State of California.

s ATTACHMENT A SEISMIC ANALYSIS OF THE GENERAL ELECTRIC NUCLEAR TEST REACTOR AND SURROUNDING STRUCTURES

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ATTACHMENT A During the oral presentation GE made to the NRC on October 28, 1977 it was postulated that a seismic event resulting in peak ground accelerations greater than 0.75 g could produce movement of certain structures with resultant reactivity insertions.

A structural analysis

  • has been completed which addressed those structures in question.

This analysis addresses the following:

i 1.

The reactor cell structure.

2.

The roof on the reactor cell.

3.

The lead shield wall at the north f ace of the main graphite pack.

4.

Control rod support structures.

5.

The reactor cell bridge crane.

6.

The fuel loading tank.

7.

The

'T' slab structure on top of the reactor.

The structural analysis was performed assuming a peak ground acceleration of 0.8 g and " Criterion Earthquake Ground Response Spectra" as supplied by EDAC.

Conclusions of the report are summarized as follows:

1.

The reactor cell will survive the postulated seismic event I

without modification.

2.

The roof on the reactor cell will survive the postulated seismic event without modification.

3.

The lead shield wall will remain intact and in position during the postulated seismic event.

4.

The control rod support structures will survive the postu-

[

lated seismic event with minor modifications.

[

  • Attached report " Seismic Analysis of Nuclear Test Reactor Cell / Room and Major Shielding Components" by K.

Dovydaitis dated November 19, i

1977.

A l.

Attachment A page 2 5.

The reactor cell bridge crane will remain in place during the postulated seismic event.

6.

The fuel loading tank will survive the postulated seismic event with the addition of a cover plate and specified braces.

7.

The

'T' slab will survive the postulated seismic event with the addition of specified support braces.

Visual inspection of the reactor cell and equipment and inspection of drawings indicated that there are no other items which could credibly damage the reactor in a manner which could result in the postulated reactivity insertions.

Based on the structure

'nalysis, modifications will be per-formed which will satisfy...a recommendation presented in the report.

Upon completion of these modifications there will be no credible mechanism resulting from the postulated seismic event which could result in reactivity insertions.

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s KE$TUTI3

~00VY0AITl 5

$TRUCTURAL ENGINEER TELE 9NONE e08/291.ssto 1180 C 0 L E as 'A N A Y EN 'J E

$AN i O E,

C A L I F O R N I A, 9)ll0 19, 1977 Noveu General Electric Company Vallecitos Nucisar Cantar Pleasanton, California 94566

SUBJECT:

SEISMIC ANALYSIS OF NUCLEAR TEST REACTUR CELL / ROOM AND MA2 R SHIELDING COMPONENTS.

Gentlemen:

In accordance with your request, I have performed the subject analysis.

The accompanying report presents the results of the analysis and specific recommendations for reifo~coment of some of the compenents.

If you have any questions, pisess call ma at your conveniacs.

Very truly yours dk' MDM Mestutis Davydaitis

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TABLE OF CONTENTS i

Page NO i

l Lattar of Transmittal TABLE OF CONTENTS j

I 4

INTRODUCTION l

l CELI / ROOM STRUCTURE Analysis 1&2 Plans & Sections 3 thru 6 SMETCH NO.1, Bridge Crans Fix 7

STORAGE TANM, Analysin 8

LEAD SHIELOING Analysis of top support 10 thru 12 Analysis of bottom support for shiniding & NTR 13 CONCRETE (TCP) SHIELOING, Analysis 14 thru 16 SMETCH NO.3, Rainforcing of shis1d support connection 17 SMETCH NO.4, Additions 1 bracing for control rod support pistas 18 s

REFERENCE, McFarland cele's & dwg's for conersta shisiding.19 thru 25 RESPONSE SPECTRA, EDAC Spectra for 'O.8g 26 c

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INTRODUCTIDN In this report we present the analysis of the responsa of the NTR Call /

~

Room and major shisiding components to an earthquaks represented by the Responsa Spectra shown on aht. 25.

The Cali/ Room containing the NTR is shown and analyzed in sheets 1 thru

6. This room will survive an earthquake represented by the spectra on sht. 26.

Although this spectra is not of sufficient magnitude to force the bridge crane inside the NTR room to jump off its tracks, a fix to prevent this pos-sibility is shown on skatch NO.1, sht. 7.

Thers is a water tank adjacent to the NTR which would everturn 0 0.8g unless the bracing shown on aht. 9 is added and the existing top plats is boltad to the tank.

The existing lead shielding in front of the tank is adequately supported, see sht's 10 thru 13.

The existing concrats shielding on top of the MTR is adequataly supported, ses shda 14 thru 16, but one of the connectons of the support to the Call / Room walls has to be rainforced see sht.17.

1 The secondary support plata for the NTR control rods has to be braced to the main plats to prevent it from moving relativa to the rest of the adjacent structure, ses sht. 18 for additional braces.

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ATTACHMENT B i i CONFIRMATORY INFORMATION ON THE GENERAL ELECTRIC l NUCLEAR TEST REACTOR

Item 1. Provide an analysis that shows the fuel temperature will not exceed about 600 F when excess reactivity equal to $.80 is inserted into the 0 core. The analysis should document the discussions'of October 28, 1977, with regard to earthquake damage mechanisms and decay heat removal and present the scenarios which might lead to reactivity insertions.

Response

A seismic analysis of the NTR cell and major components has been completed and submitted for NRC review and approval. Assessments indicate that failure of the reactor cell will not occur and only minor alterations or additions would be re-quired to insure that no damage would occur to safety systems associated with the NTR. Nevertheless, even if catastrophic non-mechanistic failure of the NTR ft::1-lities is assumed, there are no potential consequences more severe than those associated with accidents previously analyzed in APED 4444A and the Amendments. Compaction of the fuel, while essentially impossible mechanistically, would not cause the reactor to go critical since water loss, increased self shielding in the j fuel and the geometry change due to flattening of the cylindical core are all negative reactivity effects. Loss of water shuts the reactor down and no fuel melting occurs as previously discussed in the LOCA analysis. Also deformation of the core causing fuel to contact the core can structure would improve heat transfer and result in lower LOCA temperatures. The only mechanism then, which might cause fuel damage and release of fission products from the NTR fuel, are those accidents resulting from large reactivity insertions. The non-mechanistic Design Basis Accident (DBA) for the NTR assumed that in spite of mechanical devices and procedural control there could be combina-tions of independent failures which hypothetically could introduce large enough amounts of reactivity which would lead to power excursions and fuel melting. Rather than debate the amount of fuel malting which might occur, the DBA conser-vatively assumed 100% of the fuel melted and that the reactor cell was breached. The consequences of the DBA were shown to be within the guidelines set forth in Comission regulations and the details of the conservative evaluation are shown in APED 4444A. If a large seismic event were to occur and the several minor modificiations de-scribed in Attachment A have not been made, it may be hypothesized that certain.

I structures used to support the control and safety rod mechanisms as well as . experiments might fail or move in such a manner as to withdraw the control rods and experiments from the core region and prevent operation of the safety rods. The cadmium poison sheets are manually positioned entirely within the graphite reflector, have no drive mechanisms, and will not move relative to the core during a seismic event. If the reactivity addition caused by control rod and experiment movement is sufficiently large, a power excursion not terminated by a scram could occur and result in fuel melting. While the consequences are no different than those already found acceptable in the DBA analysis, a mechanism for adding this i reactivity has now been postulated. Based on the seismic analysis as presented in Attachment A and with minor altera- ] tions or additions to the NTR and surrounding structures, it is assured that a large seismic event will cause neither failure to scram nor addition of sufficient excess reactivity to cause any fuel damage. Until approval by the NRC of the analysis and the recomended modifications, the NTR will be operated in such a manner as to limit the available excess reactivity to less than that required to cause fuel damage assuming failure to scram. At full power (100 kW), this value is 0.80$ based on the analysis in APED 4444A Section 11.5.3. To determine the effects of positive reactivity additions from less than full power, reactor dynamics were simulated with the same model as described in APED 4444A Section 11.3. All transients were run with an initial power level of 1 x 10-7 kW. 0 0 Inlet water temperatures ranged from 55 F to 90 F and initial positive reactivity steps were varied from 0.60$ to 0.80$. Results of the transient analyses led to two conclusions. First, the transients are relatively long, on the order of 40 or more seconds which leads to the conclusion that the positive reactivity can be introduced in either a step or relatively long ramp without affecting the outcome.

Second, the positive reactivity feedback from the temperature coefficient while not important for the full power cases since the feedback is very small, is important for the zero
power cases.

Limiting values for the positive reactivity insertions were determined based on the acceptance criteria that the resulting transientwas terminated by bulk boiling before any steam blanketing occurred in the core. The limiting values based on this criterion are shown as~ the reactivity insertion limit values in Table 1 for various inlet water temperatures. Also in Table 1 are the maximum values of additional. ~

\\ reactivity available from the temperature coefficient which is positive at 0 temperatures less or equal to 124 F. As can be seen from the total reactivity values, limiting the total excess reactivity available from the temperature coefficient, control rods and experiments to 0.76$ or less insures that there are no mechanisms available which will cause fuel damage. Figure 1 is a plot of reactor power and peak fuel temperature vs time for a 0.66$ step insertion from 1 x-10~7kW and 65 F inlet water temperature. While the time scale is different for other limiting reactivity insertions, the peak fuel tempera-ture is virtually identical remaining in the 240 F to 250 F range during bulk boiling. It should be stressed that these transient calculations are extremely conservative since no credit is taken for the negative reactivity feedback from subcooled voids during nucleate boiling. With the large negative void coefficient of the NTR it is felt that all of the transients presented here would terminate prior to bulk boiling and realistic limits for reactivity insertions would be 0.90$ to 1.00$. 1 TABLE 1 LIMITING REACTIVITY INSERTION VALUES BASIS: Transient terminated by bulk boiling prior to any steam blanketing in core. Initial Power 1 x 10~7 kW No Scram Reactivity Inlet Reactivity

  • Insertion-Water Addition Total Limit Temperature From Temperature Reactivity

($) (OF) ($) ($) l I 1 ) 0.62 55 0.14 0.76 0.66 65 0.10 0.76 0.76 90 0.03 0.79

  • Using the temperature coefficient of do/

= -5.7 x 10-3 (T-124) d/of dt 0 where T is the water temperature in F, the reactivity added by increasing U the water temperature from T to 124 F is equal to: Reactivity Addition = 2.85 x 10-3 (T-124)2 4 l 1._- _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _

5.0 q 44 o 3.0 300 X HOT SPOT FUEL TEMPERATURE 5 / tv sr-l E m o g 200 h 2.0 E 5 8 m k REACTOR POWER R0 20 40 60 80 100 120 TIME (SECONDS) FIGURE 1. REACTOR POWER AND HOT SPOT FUEL TEMPERATURE VERSUS TIME,0.66 S STEP ~l FROM SOURCE LEVEL,66"P COOLANT INLET TEMPERATURE

Item 2. Propose technical specifications limiting the excess reactivity available for-insertion during reactor operation. Such a limitation - should apply to the combined worth of the control rods and any experiment.

Response

'The only mechanisms which might cause fuel damage and release of fission products from the NTR fuel are those transients resulting from large reactivity insertions. While the consequences of these transients are no different from those already found acceptable in the Design Basis Accider.t (DBA) analysis, it has now been i postulated that a large seismic event'could cause transients of this magnitude to occur. In order to preclude any mechanism which-could lead to fuel melting prior j to NRC review of a detailed seismic analysis and modifcations, as required, for the NTR and surrounding structures, operation of the NTR is being conducted in such a manner as to limit the excess reactivity available for insertion during reactor operation. procedures are in place which limit the total excess reactivity from the temperature coefficient, control rods and experiments to less or equal to 0.76$. i 4 i I

,o Item 3. Provide a description and analysis of the proposed attachment of experiments with the potential to introduce positive reactivity by removal or insertion into the core which precludes their moving inde-pendently of the core in the event of earthquake damage and propose any associated technical specifications.

Response

During the oral presentation to the NRC on October 28, 1977, the possibility was mentioned of' NTR operation with one or more experiments attached in such a manner as to preclude their movement relative to the core during a large seismic event. The purpose,2f this type of operation was to be able to exclude one or more experiments from the limit on excess reactivity available for insertion during a l large seismic event. Because of the inaccessability of the main graphite pack, restraints are, of necessity, tied to the existing shield wall. Since the struc-tural analysis of the shield wall has not been approved, current practice precludes I operation when the excess reactivity available from the termperature coefficient and from movement of the control rods and experiments could exceed the value specified in Item 2. Under this restriction, no restraints are required since movement of experiments relative to the core is assumed. In Section 11.4.2 of APED 4444 A, three sections of the reflector having significant reactivity effects are discussed. It should be noted that the vertical facility and the fuel loading chute graphite fillers add reactivity only upon insertion. Current operations are conducted with these graphite fillers in place and any movement would be a negative reactivity effect. If experiments are positioned in either the vertical facility and/or the fuel loading chute, the graphite reflector sections are removed and stored within the reactor cell. Thera are no credible mechanisms other than direct operator. action which could cause these reflector sections to be inserted since they require precise manual handling to position them for insertion. The horizontal facility is used for experiments whose reactivity worth on insertion can j be positive or negative. The reactivity worth of these experiments in addition to the worth from other experiments in and around the NTR core are considered in deter-mining the excess reactivity available in the event of a large seismic event. i l l l 1 l l 1

1 l o -... I ITEM 4. Provide a description and analysis of the mechanism whereby the poison shims cannot be removed as a result of earthquake damage.

RESPONSE

The NTR Poison Sheets are restrained during reactor operation by the mechanism shown in Drawing #913 E 188. In lieu of structural analysis of the restraining device, testing was performed on one of the latch mechanisms utilizing a hydraulic press. The entire latch assembly was mocked up and tested to 500 pounds without failure of the mechanism. This value is approxi-mately 100 times higher than is needed to restrain the Manual Poison j Sheets during a one g acceleration. l l Movement of the Poison Sheets are restricted by the latching device to less than 1/6 inch. i Removal and insertion of the Poison Sheets can only be accomplished by use of the special tool designed to rotate a spring loaded latch pin. It is concluded that no force induced by vibration, shock, or movement would cause the Poison Sheets to be moved relative to the core. The NTR Standard Operating Procedure 3.5 defines the requirements for Poison. Sheet changes and insures that each Poison Sheet installed in the' core during reactor operation is latched in place. ) 1

l e t,, i d c1 -. ~ ji L: -;r F e- .l,); l l c_ IM { i d %(\\ ' g- \\ 4C / / l. / l 4/ K E / e l / ~ / l j l l 1 / i ! l 76 / i Tl Iw/ i k/ / Qf 1 4 1 i -[ h lt i

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f =,, * ~ < 3 ITEM 5. Propose technical specifications whic- "equire that the poison shims be properly attached prior to' startup.

RESPONSE

As indicated in the respunse to Item 4, movement of the NTR manual j poison sheets is restrained with a latching device and detailed procedures which require verification that the poison sheets are ^ latched in place following any changes are used. These devices and procedures insure compliance with the following proposed techni-cal specification. 5.4.3 Each manual poison sheet used shall be restrained in its respective graphite reflector slot in a manner which will prevent movement relative to the reactor core during reactor operation. l 4 4 5 4 j I ~ - -m

.< es ,e i i i i \\ Item 6. Provide on-site metarological data in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability.

Response

3 Since no mechanisms exist for fuel damage and fission product release from the NTR,-on-site meteorological data is not required for the NTR safety evaluation. 3 4 l 4 i 5 s l

ase,, Item 7. Verify that your emergency procedures for VBWR include provisions for sampling water supplies in the area, if a release of radio-active liquid should occur. R_e sponse: Personnel assigned to the Reactor Irradiations organization are responsible for routine surveillance of the VBWR containment building. The Reactor Irradiations organization is also responsible for operation and maintencnce of the GETR. Procedures for inspection, access control, and facility use and modification for the VBWR are included in the GETR procedures. The GETR Emergency Plan contains instructions for actions to be taken in the event of various types of emergencies. The section discussing post-earthquake actions has been modified to require measurement of VBWR water level and if the measurement indicates loss of water, samples will be taken of off-site potable water supplies. .}}

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