ML20009G318

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Inservice Testing AND-Unit 1,Check Valve Reliability Analysis
ML20009G318
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 06/12/1981
From: Campbell P, Cullom C
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20009G315 List:
References
NUDOCS 8108040124
Download: ML20009G318 (14)
v • d • e


Text

_-

INSERVICE TESTING AN0-UNIT 1 CHECK VALVE RELIABILITY ANALYSIS JUNE 12, 1981 PATRICI A CAMPBELL CHARMAYNE CULLOM PLANT MAINTENANCE AND AVAILABILITY

\\

8108040124 810727 '

DR ADOCK 05000313 PDR

I.

Purpose The purpose of this report is to respond to a reques t f rom Performa,nce Enginee ring for reliabi-lity data to support taking exception to an ASME Section XI, Division 1, IWV 3520 A req ui remen t.

II.

Scope This analysis covers four valves, spe ci fi ca l ly as shown below:

Valve Vendor Type Size CF1A Velan Swing Check 14" CF1B Velan Swing Check 14" BS4A Anchor Tilting Disc Check 8"

BS4B Anchor Tilting Disc Check 8"

III.

Reliability and Maintainability A.

Re li a bi l i ty

,BS4A,B i

Based upon re li abi li ty an al ysi s *, the BS4A,B 1

valves heve an inherent reliability of.999 respectively for both calendar and operating hour measurements.

This was determined using the component reliability as measured by failures cited in the NPRD report **

and the requi red 90-day tes ting sequence as per ASME.

P

Using calendar hours as the measurement c ri te ri a,

these valves could be tested at period intervals of 13.47 years and still maintain a reliability of.90.

The attached calculation sheet shows the reliability probabilities associated with 5-year intervals of tes ting f requency.

Analysis of reliability of these valves using operating hours as the measurement criteria resulted in a testing frequency interval of 7.05 years would still maintain a.90 reliability factor.

The attached calculation sheet, CS-1, shows the probabilities associated with 5-year intervals of testing frequency.

1 I

CFIA,B Based upon reliability analysis *, the CFIA,B valves have an inherent reliabili ty of.999 respectively.

This was determined based upon component reliability as measured by f ailures cited by NPRD** and the required l

90-day testing sequence as per ASME.

Changing the testing sequence to the next scheduled refueling outage, 18 months hence, the associated reliability probability is.97 (see attached calculation j

sheet-2).

l Comparison of these two probabilities shows a I

di f fe rence of.029 or a reliability degradation of

3 percent.

Therefore, changing the testing frequency would not cause a significant increase in system un a vai l a bi li ty.

B.

Maintainability A survey of other nuclear plants was conducted by NUS's Nuclear Operations and Maintenance Information Se rvi ce.

The results are very promising.

It not only appears that the operating history is very good, but also shows that several plants have taken exceptions on these valves.

The responses are attached.

CS-1 CALCULATION SHEET For:

BS4A,B (8")

From:

NPRDS 1979 Annual R'eport of Cumulative Component Reliability Using Calendar Hours Number of Failures Failure Rate

=

Calendar Hours

.00000089 failures per hour

=

4949 00 Hours 90-day testing f requency ensures reliability of.999 calculated as follows:

(.00000089 failures per hour)(2160 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.2188e-4 months <br />) =.0019 = rt From Continuous Discount Factor (Table C)***

-rt,,999 e

Fi ve-yea r intervals of testing frequencies ensures the following reliabilities:

Testing Frequency Reliability (e-rt) 5 m.961 10 m.932 15 m.C96 l

20 m.861 25 s.827 l

To maintain reliability 2 90%:

Testing f requency =(000 0089) hours x 365 d s x 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> / day 13.47 years

=

l i

I l

Using Operating Hours

.0000017 failures per hour

=

84 0

tours l

.999 reliability (e-rt) 90-day testing:

s 5-year intervals of testing frequencies:

Testing F req ue n cy Reliability (e-rt) l 5

s.932 10 s.869 15 s.803 20 s.748 25 s.705 To maintain reliability t 90%

Testing frequency =

5 Y

(

hours ( g gg)

= 7.05 years

CS-2 For:

CFIA,B (14")

90-day testing interval extended to 18-month testing interval:

(Using Operating Hours) 29 Fail ures

.0000025 failures per hour

=

11608000 Hou rs 90 days -

s.99 reliabili ty (e-rt)

(rt =.005) 18 months -

s.970 reliabili ty (rt =.03)

,--..__.,,_._,__,..,..,m,

4 BIBLIOGRAPHY J

  • Powe r Plant Availability Engineering Basic Techniques in Availability Engineering Prepared by Pickard, Howe and Garick, Inc. for Electric Research Institute Part 2. Reliability Analysis Page 2-7
    • NPRD Report A03 (Part 2)

Annual Report of Cumulative Component Reliability /Nuclea r Plant Reliability Data System Report Pe ri o d ;

7/74 - 12/79

-rt

      • Table C - Continuous Discount Factor - e Quantitative Analysis for Business Decisions Bierman Bonini Housman Thi rd Edi tion, 1969 (see copy attached)

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APPENOlX OF TABLES 465

!.i TABLE C f

Continuous Discount Factor-e'"

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PLANT MANUAL SECTION:

PROCEDUREA*/ORK PLAN TITLE:

NO:

ASME CODE SECTION XI OPERATIONAL J

OPERATTONAI ADMIN.

READINESS TESTING 1015.06 O-PAGE 8 of 69 ARKANSAS NUCLEAR ONE aevision 3 oare

//16/81 CHANGE DATE 6.5.3 This submittal shall include a listing of all additions, deletions and revisions to the existing programs that have been implemented since the last sebmittal to the NRC.

This submittal shall also include justiidcation for any relief requests from specific requirements of one Section XI of the ASME Code.

6.5.4 The submittal shall be issued by the Plant Analysis Super-intendent after approval by the PSC.

6.6 IST Program Records The IST Coordinator (s) shall maintain a working file of Inservice Test Program records which include:

6.6.1 Pump and valve test data.

This file should include selected data from the current and the previous year.

6.6.2 All request for additions, deletions and revisions to the IST Program.

6.6.3 Baseline test data for each re-run of baseline data as re-quired following maintenance or modifications.

6.6.4 All NRC submittals and correspondence involving the IST program.

6.7 Valve testing in accordance with the ASME Code,Section XI, shall commence within two hours after a cold shutdown condition is achieved but not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown and continue until complete or the plant is ready to return to power.

Completion of all valve testing is not a prerequisite to return to power. Any testing not completed at one cold shutdown will be performed during any subse-quent cold shutdowns that may occur before refueling to meet the Code specified testing frequency.

Exceptions to the 46 hour5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br /> start time will be taken for planned cold shutdowns where all valve testing in Cold Shutdown mode identified in our Inservice Testing Program will be completed.

7.0 FOIc!S AND ATTACllMENTS Form 1015.06A, IST Program - Revision Control - Unit One IST Program - Unit Two IST Program - Guidance for ASME Section XI category classification of pumps and valves.

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