ML20206M984

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Rev a to Aging Analysis of Non-Metallic Age Sensitive Matls of Component Cooling Water Pump
ML20206M984
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 03/01/1985
From:
WYLE LABORATORIES
To:
Shared Package
ML20206M077 List:
References
57689, 57689-RA, NUDOCS 8704200334
Download: ML20206M984 (12)
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WYLE peomuomes scawc saavcas a snnus oaov, ENGINEERING Wyle Repe,, No. 37689 wt$ TERN OPERATION $, NORCO FACILITY ODy NES 57689 184l HILL $1DE AVfNVE, NORCO. CALIFORNIA e1740 VII ' Wyle Job No-AttA CODE 714-7274e71 twx *104321204 titeCory (7:4)727ce7:

Customer P.O. No.14926-EQ01Q Task 7 Toto! Pages this Report 9 oote. 12/21/8L Revision A 3/1/85 r '

AGING ANALYSIS OF NON-METALLIC AGE SENSITIVE M ATERIALS OF COMPONENT COOLING WATER PUMP

i. .J PREPARED BY: 42 8a 3 -

VERIFIED BY- MM M

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APPROVED BY- - - y6# " 7 ---

QUALITY ASSURANCE: M G;704200334 870415 PDR ADOCK 05000498 A

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WYLE LAsonATORIES SCIENTIFIC SERVICES & SYSTEMS GROUP ,

page i O REVISIONS Rev.No. 'Date Pages Affected Preparer Reviewer QA PE Description of Changes A -

3/1/85 6,7,8,9 b N k g/g Incorporated customer's comments ,_

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Muaonatomas x mesaavcesasystewsonow REPORT NO. 57689 WEST 88N OPtRADONE NORCO PACluTY ,,,, go 2 s .

TABLE OF CONTENTS Page No.

1.0 SCOPE........................................................3 1.1 Objective......................................................3 1.2 Applicable Qualification Standard and Document . . . . . . . . . . . . . . . . . . . . 3 1.3 Equipment Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 D EFINITIO N OF SERVICE CONDITION . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.0 EV ALU ATIO N C RITERI A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.1 Evaluation of Susceptibility to . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Radiation Degradation 3.2 Evaluation of Susceptibility to . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Time / Temperature Related Mechanism fsv) 4.0 E V A L U AT I O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 l

4.1 Radiation......................................................7 4.2 The r m al A gi ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 5.0 C O N C L U SIO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 6.0 R E F E R EN C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 l

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REPORT NO_ 97Alte EWTWNoPORA W NOSCOPACIUTY ,4, ,,o t V .

1.0 SCOPE ,

This document was prepared by Wyle Laboratories for Bechtel Energy Corporation (BEC) for equipment to be used in the South Texas Project Electric Generating Station. ,

1.1 Objectives The purpose of this report is to perform an aging analysis of non-metallic materials used in the Component Cooling Water Pumps.

The aging analysis of non-metallic m.terials was based on the criteria of susceptibility to time / temperature and radiation mechanisms.

l Damage levels and calculated lives were determined solely on the individual l

effects of the radiation and time / temperature related aging mechanisms.

12 Applicable Qualification Standards and Documents e IEEE 323-1974 " Standard for Qualifying Class IE Equipment for Nuclear t O Power Generating Stations".

! o IEEE 627-1980 " Standard for Design Qualification of Safety Systems l Equipment Used in Nuclear Power Generating Stations".

o Bechtel Specification 4A479ES1018, Rev. 2, " Specification for the Environmental Qualification of Safety-Related Electrical and Mechanical Equipment for the Houston Lighting and Power Company South Texas Project Electric Generating Station".

o Wyle Laboratories Western Test and Engineering, Quality Assurance Manual,380 Rev. D dated 15 April 1984.

1.3 Equipment Description The subject of this analysis is the component cooling water pumps. The tag number for these pumps are:

Tag Number Unit 3R20lNPA101A 1 3R20lNPA101B 1 3R20lNPA101C 1 3R202NPA201A 2 O 3R202NPA201B 3R202NPA201C 2

2

REPORT NO. 57689 Monenes u see.m seaw.es a sve== enow WESTMN oPHAM NotCo FAClufY pagg e.o 4 O  !

2.0 DEFINITION OF SERVICE CONDITION BEC has specified the following environmental service condition (Ref.1).

Normal Condition Abnormal Condition Accident Max. Min. Max. Min. Conditions Temperature OF 120 50 120 50 125 l Pressure psig Slightly N/A 0.3 Negative Relative Humidity % 80 20 N/A 100 Radiation Gamma, Rads 103 N/A 130 3.0 EVALUATION CRITERIA 3.1 Evaluation of Susceptibility to Radiation Degradation The approach for evaluating radiation sensitive materials of the pumps is a two-step process:

1. Research Wyle Laboratories Aging Library for information on threshold levels, severe damage levels, degradation characteristics, and failure criteria.
2. Provide evaluation based on potential material degradation and ability to perform its design function after exposure to the specified radiation dosage.

3.2 Evaluation of Susceptibility to Time / Temperature Related Mechanisms For many organic matgerials, it is known that the degradation process can be defined by a single temperature-dependent reaction that follows the Arrhenius equation (Ref. 2 and 3):

k = A exp (-(Ea/kgT))

where, k = reaction rate A = frequency factor exp = exponent to base e Ea = activation energy kB = Boltzmann's Constant (8.617 x 10-SeV/K) ,

e p T = absolute temperature l V  !

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REPORT NO 57629  ;

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wasunn onaAnmonco paciun ,,,, ,,o 5 3.0 EVALUATION CRITERIA, (Continued) 3.2 Evaluation of Susceptibility to Time / Temperature Related Mechanisms,(Continued)

It is further r.oted that, for many reactions, the activation energy can be considered to be constant over the applicable temperature range. Life is assumed to be inversely proportional to the chemical reaction rate (Ref. 2 and 4). In terms of life, and after converting to Napierian base togarithms, equation (1) becomes:

In (life) = (Ea/k B)(1/T) + Constant (2)

Equation (2) has the algebraic form:

y = mx + b, where y = In(life) x = 1/T m = Ea/kB, constant for single dominant reactions b = constant The constants, m and b, can be estimated by fitting the experimental data in the form of In(life) versus 1/T to the above simple linear relationship.

For example, Dow Corning #732 RTV Silicone Rubber with a failure criterion of 50%

elongation:

In(life) = 8956.8356(1/T) - 11.4998 for a baseline temperature of 313K (1040F) life = 3.09 x 103years 7

M usenavones seein cseavessaavs,susonow nEPORT NO 57689 westesN oPERAnoNL NoRoo PAcufv .

, , , , , 6 Revision A 4.0 ' EVALUATION Table I lists the non-metallic parts of the pump.

TABLEI NON-METALLIC PARTS ITEM PART MATERIAL 1 Gasket (Casing 3oint) Asbestos 2 Gasket (Shaft Sleeves) Asbestos 3 Gasket (Outboard / Inboard Glycerine Paper Bearing Cover) 4 Mechanical Seal Buna-N/Viton The outboard / inboard bearing cover gaskets do not come in contact with the media that pump is puming. The function of these gaskets are to prevent excessive bearing lubricant leakage. These gaskets are considered not safety related and therefore exempt from aging and radiation requirement.

Pump bearings are metallic components, and are not affected by time / temperature aging and specified radiation. Life of a bearing depends on proper design, lubricant and contaiminants. Contaminants, operating temperature and radiation affect the ability of the lubricant. Therefore bearing and its lubricant should be treated as replaceable items with their replacement interval depending on manufacturer recommendation and end user maintenance and inspection program. This analysis will show if normal and accident radiation has any significant effect on the lubricant.

The manufacturer catalog shows that the mechanical seal contains age sensitive 'O' rings (Ref. 9). These 'O' rings are either made of Viton or Buna-N (Ref.10). The mechanical seal does not contain any other age sensitive parts.

The non-metallic parts are internal to the pump and therefore not affected by specified environment pressure and relative humidity. The effect of radiation and time / temperature on these materials is discussed in the following paragraphs.  ;

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RErORT NO Monmass u see.mac senessa svsonsonow

  • wgSTGAN oPERAftoseI5NoSCO PAClufY pm ,,o

. Revision A O

4.1 Radiation

{ Asbestos material is resistant to the effects of the radiation. The radiation damage threshold level for asbestos is 3.96 x 1015 rads (Ref. 5). Reference 6

- is a study of the effects of radiatien on organic materials. The lowest radiation damage threshold identified in this reference is 104 rads. This radiation damage threshold exceeds the requirement by a factor of 8.

Therefore, the eficct of radiation on the non-metallic part of the pump is insignificant.

4.2 Thermal Aging This analysis takes into account the effects of a) normal, b) abnormal and c) accident temperature.

Asbestos is a silicate mineral. It is heat resistant, chemically inert, and insensitive to time / temperature effects.

The 'O' rings used in the mechanical seal are made of either Viton or Buna-N.

These two materials were analyzed for the effect of time / temperature aging.

The analysis consisted of a) calculating the expected life of the material, b) i subtracting the required worst case temperature duration from the life and, l

c) using the remaining life, calculate the life of the material for use at normal service temperature.

t' Ea = 0.68 ior Buna-N (Ref. 7)

Slope : 7843.958 for Buna-N (Ref. 7)

Intercept = -14.2945 for Buna-N (Ref. 7)

Ea = 1.09 for Viton (Ref. 8)

Slope = 12639.561 for Viton (Ref. 8)

Intercept = -19.5298 for Viton (Ref. 8)

The accident temperature including 150F margin is 1400F (600C). The Buna-i N life is:

In (life) = 7843.958 -14.2945 333 life = 438.29 days at the accident temperature remaining life = 438.29 -30 days = 408.29 days at accident temperature The worst case normal / abnormal temperature1 is 1250F ~

- 1 (51.60C)

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Normal service life = 408.29 days Exp('0.68lXi7-5 X8))

L Normal service life = 931.46 days

= 2.55 years at normal service temperature 1200F G

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57689 M

_- scom,c sences a svenus enov, REPORT NO.

, west:AN opfaAnoNS, NotCo PAQuTY pg, g 8 Revision A b .

l 4.0. EVALUATION, (Continued) r 4.2 Thermal Aging The life of Viton for this application exceeds 100 years. This analysis showed that Buna-N is more susceptible to the effects of time / temperature aging than Viton. The replacement interval for Buna-N 'O' ring is 2.55 years. Viton

'O' ring has a qualified life of 40 years.

This analysis assumes the 'O' rings are stored per manufacturer recommendation and used during recommended shelf life.

5.0 CONCLUSION

The aging mechanisms considered in this report are radiation and time / temperature. The non-metallic materials were found not sensitive to the specified radiation.

Asbestos is a non-organic material, and therefore insensitive to time / temperature aging. Inboard / outboard gaskets were exempt from aging and radiation requirements.

The 'O' rings used in mechanical seal are either made of Buna-N or Viton.

Buna-N was found more susceptible to the effect of time / temperature.

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M use==es scome es=ca a sv =s onow mEPORT NO.

,, 9 westema anunows.nonco racam Revision A

6.0 REFERENCES

1. Bechtel Energy Task Description, Task No. 4022EQl.
2. "lEEE Cuide for Statistical Analysis of Thermal Life Test Data,"IEEE . 101-1972, Library Code 265-80.
3. "A Review of Equipment Aging Theory and Technology", S.P. Carfagno and R.3. Gibson, Frankline Research Center, Electric Power Research Report No. EPRI-NP-1558, Library Code 600-62.
4. Handbook of Enaineering Fundamentals, 3rd Edition, O.W. Eshbach and M. Sanders, pp. 284, John Wiley & Sons,1975, Library Code 247-80.
5. Effects of Radiation on Materials and Components, John F. Kircher and Richard E. Bowman, Reinhold Publishing Corporation, pp 341.
6. " Radiation Effects on Organic Materials in Nuclear Plants", M.B. Bruce and M.V. Davis, EPRI Report No. NP-2129, Library Code 506-81 A. -
7. Design Guide for Reactor Cover Gas Elastomer Seals, Atomic International, Division of Rockwell International, AI-AEC, 13145, N

) Library Code 663-81.

8. Dupont Report No. V-D-3-301, Wyle Aging Library 386-80.
9. Dura Seal, the Engineered Mechanical Seal, Durametallic form 520-83 BPC.
10. Wyle Contact Report Dated 12/13/84, Contacted by P. Danesh Agency: Durametallic Corporation, Person: Larry Park.

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ENVIRONMENTAL QUALIFICATION

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DOCUMENT NO. 80278-756

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SEAL RETROFIT 373- e.cai L N.

A 374 JUST'FICATION OF RETROFIT SEAL MODIFICATI^"3 FOR NBD-53 DAMPERS 14926-4168-00267-BVA 14926-8168-0Wg-BVA APPENDIX E

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