ML20099D166

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Proposed Tech Specs Relaxing Certain Overly Conservative Surveillance & Testing Requirements for Auxiliary Feedwater Pumps to Correspond to ASME Boiler & Pressure Vessel Code, Section Xi,Subsection 1WP
ML20099D166
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 11/16/1984
From:
DUKE POWER CO.
To:
Shared Package
ML20099D147 List:
References
TAC-56478, TAC-56479, NUDOCS 8411200230
Download: ML20099D166 (10)
v • d • e


Text

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Atit chment I

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h:t  ; PLANT SYSTEMS d

. AUXILIARY FEE'DWATER S'YSTEM

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LIMITING CONDITION FOR OPERATION J 3.7.1.2f At;1eastithree independent steam generator. auxiliary. feedwater puerps land associated flow' paths'shall be OPERABLE withr

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. a .' Two motor-driven auxiliary feedwater pumps, each capable' of being powered from separate. emergency; busses,.and

b. One steam turbine-driven auxiliary feedwater pump capable'of being ipowered from an OPERABLE steam supply system.

APPLICABILIT_Y: . MODES 1, 2, and 3.

' ACTION:

a. With' one auxiliary.feedwater pump inoperable, Lrestore the required auxiliary.feedwater. pumps to~0PERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or:be in

'at.least-HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />'and in HOT SHUTDOWN.

-within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

b. With two auxiliary feedwater pumps inoperable, be in at least HOT'-

STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in-HOT SHUTDOWN within~the following 6-hours.

c. .With three. auxiliary feedwater pumps inoperable, immediately. initiate corrective action to restore at least one auxiliary feedwater pump to operable' status as scon as possible.

SURVEILLANCE REQUIREMENTS

.4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a. At least once per 31 days by:
1) Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its

..M., correct position; J 2) Verifying that each automatic valve in the flow path is in the

.m fully open position whenever the Auxiliary Feedwater System is

' o" placed in automatic control or when above 10% RATED THERMAL y POWER; and b.

d "Not applicable with steam pressure less than 900 psig.

McGUIRE - UNITS 11 and 2 3/4 7-4

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<iSURVEILLANCE REQUIREMENTS (ContinuedF -

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- ~ 3)i nVerifyingLthat _the isolation v'alves L.ini the:: auxiliary feedwaterf t [

" . suction'line from,the. upper surge tanks. are 'open with power to '

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.the valv'e operators removed. '

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. b. .At-least)once per 92. days by: '

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1); ; Verifying that each motor-driven pump"is:te'stedlin:accordance' ~

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~ twith:ASME Boiler and Pressure = Vessel Code, Section.XI, Sub--

(section:IWP'and develops la' discharge pressure greater.than ori cequal tol1210 psig atla' flow of; greater than or(equal to:450'

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^m .,

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-2)FVerifyingLthat:.'the:steamiturbine-drivenpumpidevelopskadis-charge pressure of greater than or equal lto 1210 psig;at a' flow.

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'of-greater than or equal;to 900

.- -  : supply pressure'is greater than'gpm 900 psigi when;Thethe secondary provisions ofL steam',

-specification 4.0.4;are not applicable forLentry into MODE:3.

c. At least'onceiper~18 months during shutdown'by:"

'1) ' Verifying thatLeach automatic valve in'the flow path actuatesjto

'its correct position upon receipt-of!an' Auxiliary Feedwater:

Actuation test signal, Verifsingthateachauxiliaryfeedwaterpump1startsasdesigned-2)-

. automatically upon receipt of an Auxiliary Feedwater Actuation

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test signal, and 3). : Verifying that the valve in the suction line of each auxiliary feedwater pump from the Nuclear Service Water: System auto-matica11y actuates-to its full..open position within less than or. -

equal to 13 seconds on a low Suction Pressure test signal.'

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i Justification and Safety Analysis 1 -

Thd motor-driveniand the turbine-driven' auxiliary.feedwater pumps are .r

. . tested'at"least once per 31l days :in accordance withjTechnical, Specification

~4.7.1.2-a." 1) and 2). in' order. to '.verifyf theideveloped - discharge pres'sure and?

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i flow 2 ' The' auxiliary feedwater pumps ar'e ASME Class 3 centrifugal pumps which .

, come under;the; scope of ASME; Boiler andtPressure Vessel; Code..Section'XI, JSubsection IWP.' :McGuire' tis committed-to the 1980 edition of the ASME Boiler-t and Pressure Vessel 1Codei 'According to this ; code; the~ motor-driven -and 'the yc ' turbine. driven a'uxiliary;feedwater-pumps'should be' tested on a qu'arterlyibasis,.

(once every ;92 days). The'. surveillance and testing requiremen's t contained;in

the'ASME code for auxiliary feedwater pumps are conservative...

'It'is the intent J ofIDuke' Power' Company:to; switch;over to the ASME code surveillance 1 -

requirement- af ter. obtaining ~ NRC concurrence in this . matter.; .The .following 6 'pages i

.  : provide the . test 'results for. the auxiliary feedwater pumps since 1981. : The'testJ

results demonstrate the high reliability of;these pumps - Duke Power Company.

L 1 submits that,quarterlyitesting willLbe sufficient to= detect pump failure and-assure operational readiness and will reduce unnecessary : pump wear. - The'new- "

Ite' sting frequency will. be ~consistentDwith' other safety' related ' pump surveillance and testing.:

In' addition theLauxiliary feedwater-pumps'will be rotated on a monthly basis

to assureLthe lubrication;of the journal bearings ius suggested by the-NRC.

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-The proposed changes:would not compromise the operational readiness of the'..

auxiliary feedwater pumps.and would reduce lthe pumpLwear by reducing the number

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of pump starts. : The proposed changes to the McGuire' Technical Specifications '

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do not have any adverse safety. implications.

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McGUIRE NUCLEAR STATION UNIT 1.1-1 ,

. TURBINE-DRIVEN AUXILIARY 1EEDWATER PUMPi t

% 1 TEST RESULTS i .M

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1: Date TestedL. _

. Results. 7

[ Acceptable-- Unacceptable' Llieason For Failure 1

' 04-12181
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07-08-81L x'::

i08-10-81: '

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'09-15-81c tx (f :10-05_-81: :x 11~-04-81 x

12-31-81

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01-27-82 ~ -;x- s 11-82'- .

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04-19-82. -x 19-82:

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  • 08-19-82 -x 09-16 -x 10-18-82. x -

'011-22-82 -x 12-21-82. x-

- Steam Generator Modification ,

04-29283 x

. 01-83~ x l' ~06-27 .x 07-25-83 x

. 08-30-83 -x 09-19-83 x

' 09-26-83 1 10-24-83 x
11-19-83 x

.12-19-83 ' x.

01-26-84: x

.02-13-84 x LRefueling 04-26-84 x

05-24-84 x Pump parameters acceptable /ISA-49 failed.

response time 21-84' x

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I P'eriodic Maintenance Retest WMS/nem

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F _. 09-17-82 .x ' Failed Horizontal'

Vibration Readings"

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10-22-82 -x '

11-23-82 x

'12-23-82 x. '

-Steam Generator Modification 26 83' x -

105-24'-83. ,

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06-21-83

x. High Horizontal Bearing

'07-06-83 x Vibrations / Alert-Range

. Bimonthly Testing 07-20-83' x

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'10-28-83; - x 11-23-83 x ~#

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HOTOR-DRIVEN' AUXILIARY FEEDWATER PUMPS-: B' ,'

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-TEST.RESULTS^ <

.. Results ' '

.Date Tested'

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Reasontfor Failure-K - ..

J03 10-81 104-11-81c x-18-81' ,

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12-29-81~. x-01-11-821 .- 1x-01-26 x 02-24-82

-x 103-24-82 x 04-23-82 .x' 05-21-82' ..x- .

L06-I8-82. ~x' 07-22-82 x-08-23 x 09-20 x 10-20-82 x 11-23-82 x 12-23-82 x Vibration' Meter Out'of Calibration 12-30-82 x Steam Generator Modification 26-83 x 05 08-83 x 06-13-83 x 07-06-83 x 03-83 x.

08-31-83 x-09-28-83 x.

10-26-83' x-11-23-83' x 22-83. x 01-19-84-- x 01-27-841 '

'02-16-84 x

. Refueling

.-04-19-84 x 05-15-84 .x 06-12-84 x '

I Periodic Maintenance Retest-liMS/nen

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i-Reason for Failure-

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'Stican Generator Modification- . .

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312-01-83: .x Pump APiiLow Limit

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, Discharge Pressure Gauge.-

Out'of Calibration <-

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1 03-21-84' x

'04-18-84/ x.16-84L x- i

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McGUIRE NUCLEAR -STATION UNIT 2:

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.: Date Testedi

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-Steam Generator. Modification:

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TEST RESULTS

, ., . . . . ;Results-5 Date' Tested'  ! Acceptable- Unacceptable-

" Reason'for' Failure -

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04-20-83, ,

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-' Steam Generator' Modification

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08-11 x >-

208-13-83 -x 08-83 ~. x '

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7 Analysis'of Sianificant HazardsEConsideration- -

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, Pursuant'to! requirements (ofl10CFR50.91,?this analysis;provides;a determination 2

%1 , :that;tho' proposed changesLto.the Technical' Specifications do not' involve'anyl W Leignificant hazards': consideration,jasidefined by 10CFR50.92.;- '

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?TheLyroposed Technical' Specifications ~ change the overlys conservative current:

,p Ispecifications.to the ASME Boi1~eriand.-Pressure, Vessel Code l(Section'XI,1 Subsection, 3~ . 1 - 71WP) surveillance 1anditesting; requirements.-. The-resulting Technical, Specifications-7 will continue' to,be! conservative.. :In: view of' the high reliabilityiof .the auxiliary

feedwater, pumps,(theLsameitype of testing'as. applicable 1.to other
safety:.related,

. pumps is1 considered sufficientLand/ appropriate. -The proposedichangesldo.not-introduce.any  ; new accident.' mechanisms. 'Due?to:high' reliability;and redundancy:of-Ethe a'uxiliary feedwater pumps there.will be no change;in the. consequences of any1'

.' accidents. con'sidered in;the FSAR.D -

.Therafore the' proposed changes would not:

1)' + Involve a significant; increase in thelprobabilitiy or~

- consequences offan accident previously evaluated; or~ -

2) Create .the possibility of' a.new or.ldifferent kind .of l

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accident 1from any'. accident previously; evaluated; or' a . t

,-3)-. , Involve a;significant reduction in.a margin'of' safety.: , '

~ Based upon the. preceding analysis. . Duke (Power . Company concludes that the pro-:

. posed amendments do;not'involveLaisignificant; hazards' consideration.

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