LIC-98-0066, Documents Info Provided in 980422 Telcon Re Clarification of Amend Request Re Auxiliary Feedwater Sys.Addl Detailed Performance History Encl

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Documents Info Provided in 980422 Telcon Re Clarification of Amend Request Re Auxiliary Feedwater Sys.Addl Detailed Performance History Encl
ML20247M723
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 05/18/1998
From: Gambhir S
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-98-0066, LIC-98-66, NUDOCS 9805260354
Download: ML20247M723 (12)


Text

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Onaha PdaicPonerGwict 444 South sah Street Mat Onda.NebrasAs 681@2247 May 18,1998 LIC-98-0066 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington D.C. 20555

References:

1. Docket 50-285
2. Letter from OPPD (S. K. Gambhir) to NRC (Document Control Desk) dated October 3,1997 (LIC-97-0155)

Subject:

Clarification and AdditionalInformation for Application for Amendment of Operating License - Auxiliary Feedwater System in Reference 2, Omaha Public Power District (OPPD) requested an amendment to Fod Calhoun Station (FCS) Technical Specifications Section 3.9 associated with surveillance requirements for the Auxiliary Feedwater (AFW) system. During a telephone conference call including NRC/NRR staff and OPPD personnel on April 22,1998, OPPD clarified one of the purposes of the requested amendment and provided some performance history for the Auxiliary Feedwater pumps. As requested by the NRC, this letter documents the information provided on the conference call and provides additional detailed pe formance history. l q

Steam Driven Auxiliary Feedwater Pumo (FW-10) l Testing There are two surveillance tests normally performed for this pump. The first test verifies operability of the pump on a monthly basis, and verifies the ability of the pump to meet the [

(nominal) 140 psid differential pressure between the pun p discharge and the steam in5t pressure to the pump turbine driver, at normal main steam pressures. /

The second test verifies the operability of the pump on a quarterly basis, in accordance with the in.orvice Testing (IST) program. This test also verifies the ability of the pump to meet the 1 (nominal) 140 psid differential pressure. However, in this test a steam pressure signal is gf j injected into the speed control loop corresponding to the highest steam generator pressure that /j/hy AFW would be required to operate under. This test verifies that, even under worst case l l

conditions, the required amount of AFW flow can still be attained. I l The amendment request proposes no changes to the way OPPD currently tests the pump. The request does propose removal of the incorrect discharge pressure verification criterion (240 psig above steam generator pressure) from Technical Specification 3.9(2); the IST program will  ;

administer and control this performance criterion. The quarterly IST surveillance test refers to l an engineering calculation for the value of this differential pressure parameter.

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9805260354 980518' PDR ADOCK 05000285 P PDR ..,~pnent eth Equal Opportunrry

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p U. S. Nuclear Regulatory Commission L LIC-98-dO66 )

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Pump Performance History LAttached are two sets of trend graphs and data. The first set shows a brief history of the monthly tests. Trending of this data started in August of 1997. The first monthly test graph shows the As-Found differential pressure, and the second monthly test graph shows the As-Left  ;

differential pressure. Adjustment of the differential pressure controller is allowed under this i surveillance test.. Also, notice that the monthly test is not performed every third month. OPPD has a provision in the monthly test that, if the quarterly IST surveillance test is performed within the surveillance window of the monthly test, then the monthly test can be administratively closed out. This is because the quarterly test accomplishes everything the monthly test does, in addition to the quarterly IST requirements.-

Please note the failure of the monthly test in September of 1997, in which the controller could not be adjusted into specification (178 psid). Maintenance was performed following this failure, and the pump tested satisfactorily.. The maintenance included replacement of the pneumatic

' controller and derivative unit. The post-maintenance performance of the monthly test had an expected as-found out-of-tolerance (152 psid), but was subsequently adjusted back into specification satisfactorily (144 psid as-left).

The second set of trend graphs and data show the performance history of pump performance during the quarterly surveillance test. The graph only goes back to August of 1996, but the attached data tables show the pedormance back to January of 1993.

As the calculation for the required differential pressure has been revised over the years, the tolerance applied to this parameter has widened from 140 (i 5) psid, to 140 (* 10) psid, to the current 140 (+ 10, - 20) psid.

Please note the two consecutive quarters (2/11/97 and 4/16/97) where the pump failed to meet the differential pressure criterion. These failures and the failure of the monthly test on 9/19/97 were most likely caused by a piece of foreign material in the small clearances of the controller and/or derivative unit in the speed control pneumatic instrument loop. The steam driven AFW pump remains in Maintenance Rule Category (a)(1), pending completion of an action plan and an 18 month monitoring period of satisfactory performance with no functional failures.

The corrective actions and enhancements made during the current refueling outage include:

1. - Addition of an isolation valve in the steam pressure sensing line, which will allow the use of an existing 0 - 200 psig differential pressure gauge. This will provide for a significant improvement in accuracy and instrument uncertainty, and subsequently allow for an even wider tolerance band on the pump dP requirement.
2. Replacement of the upstream air supply filter regulator with one that includes a 2 micron filter. This should help provide higher quality air to the pneumatic speed control loop instruments.

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U. S. Nuclear Regulatory Commission

. LIC-98-dO66

.Page 3

3. Replacement of all instrument air supply and signal tubing and fittings. This will preclude the possibility that any foreign material or particles inside the old tubing or fittings might break loose during pump operation and hamper proper operation of the pneumatic instruments.

Motor Driven Auxiliarv Feedwater Pumo (F@4)

The motor driven AFW pump has performed satisfactorily. As can be seen from the trend graph and data tables, developed head (differential r *ssure) is very consistent. The same allowance which applies to the steam driven AFW pump applies to the motor driven AFW pump, i.e., if the quarterly test is performed within the surveillance window of the monthly test, the monthly test can be administratively closed out.

Please contact me if you have any questions.

Si rely, k

N S. K.

ambhir Division Manager _.

Engineering & Operations Support TCM/ tem Attachments C: E. W. Merschoff, NRC Regional Administrator, Region IV L. R. Wharton, NRC Project Manager W. C. Walker, NRC Senior Resident inspector Winston & Mrawn i

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LIC-98-0066 Attachments FW-10 Monthly Test Data

- FW-10 Quarterly Test Data FW-6 Quarterly Test Data Annual AFW System Unavailability i

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. Omehn Public Pow:r District LIC-98-0066 Attachment OP-ST-AFW-0004 AUXILIARY FEEDWATER PUMP FW-10 OPERABILITYTEST DIFF'ERENTIAL PRESSURE FROM PUMP DISCHARGE PRESSURE AND STEAM INLET PRESSURE

. COMPLETE As Found DIFF DIFF PRESS DIFF PRESS As Left DATE DPI-1038 Lower Limit Upper Limit DIFF PRESS step 7.6 DPI-1038 03/03/98 148.00 120.00 150.00 148.00 02/05/98 146.00 120.00 150.00 146.00 12/09/97 146.00 120.00 150.00 146.00 11/14/97 145.00 120.00 150.00 145.00 09/19/97 152.00 120.00 150.00 144.00 09/19/97 178.00 120.00 150.00 178.00 08/25/97 136.00 120.00 150.00 136.00 l

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. Omahm Public Powzr District LIC-98-0066 Attachm nt AUXILIARY FEEDWATER PUMP FW-10 TEST AND STEAM ISOLATION VALVE TEST l _

SE-ST-AFW-3006 COMPLETE DELTA P REFERENCE LOW HIGH DATE 1025 VALUE ACTION ACTION 01/08/98 140.0 140.0 120.0 150.0 10/17/97 140.0 140.0 120.0 150.0 07/28/97 125.0 140.0 120.0 150.0 06/05/97 120.0 140.0 120.0 150.0 04/17/97 140.0 140.0 130.0m -

150.0 04/16/97 120.0 140.0 130.0 i 150.0 02/12/97 130.0 140.0 130.0 150.0 02/11/97 100.0 140.0 130.0 150.0 l 11/27/96 137.0 140.0 130.0 150.0 09/03/96 140.0 140.0 130.0 150.0  ;

08/27/96 130.0 140.0 130.0 150.0 l 06/07/96 140.0 140.0 130.0 150.0 l 03/11/96 130.0 140.0 130.0 150.0 12/21/95 130.0 140.0 130.0 150.0 09/29/95 140.0 140.0 130.0 150.0 07/06/95 140.0 140.0 130.0 150.0 04/11/95 140.0 140.0 130.0 150.0 02/02/95 130.0 140.0 130.0 150.0 12/07/94 130.0 140.0 130.0 150.0 08/26/94 130.0 140.0 130.0 150.0 l 06/24/94 130.0 140.0 130.0 150.0 03/07/94 130.0 140.0 130.0 150.0 01/04/94 130.0 140.0 130.0 150.0 01/04/94 140.0 130.0 150.0 09/20/93 135.0 135.0 145.0 06/28/93 140.0 135.0 145.0 04/05/93 135.0 135.0 145.0 01/11/93 135.0 135.0 145.0 l

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. Omaha Public Power District LIC-98-0066 Attachment AUXILIARY FEEDWATER PUMP FW-6 AND CHECK VALVE TEST ST = SE-ST-AFW-3005 COMPLETE DISCHARGE SUCTION DIFFERENTIAL REFERENCE LOW HIGH DATE PRESSURE PRESSURE PRESSURE VALUE ACTION ACTION 03/24/98 I

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12/30/97 1140.0 25.0 1115.0 1085, 1232 1120j _

10/06/97 1130.0 25.0 1105.0 1120l 1085) 1232 08/20/9f~ 1140.0] 25.03 1115.0 l 1128 1232 05/28/97 1085(

1140.0 l 25.0 i 1115.0 1 1120 1085j 1232 02/27/97 1125.0 990i 1210 25.0 L 1100.o2 11ooL . -

12/05/96 1160.0 1135.5 1210 24.5 { 1100l 990[

09/12/96 1125.0 25.5 ' 1094.5 1100j 990l 1210 06/25/96 1120.0 l 23.7 1100! 990! 1210 1096.3 } ~ ~

03/28/96 1130.d" 25.0 1105T0 ! 1100[' 1210 990]

01/05/967 1120.0 24.51 1095.5 l ~ 1100l 990l 1210~

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- 03/01/94 i 1130.0 24.5 1105.5 1100I- 990 1133 12/09/93 1125.0 24.51 110055 1100l 990 1133 ~

09/14/93 1133.0 24.5 1108.5 " 1100i 990 1133 06/22/93 1130.0 24.0 1106.0 95dl 1133 110K 03/30/93 -

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