ML17333A468

Provides Third 10-yr Interval in-service Pump Test Plan & Requests Relief from ASME Section XI Requirements

ML17333A468
Person / Time
Site:	Cook
Issue date:	06/12/1996
From:	Fitzpatrick E AMERICAN ELECTRIC POWER CO., INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17333A469	List: ML17333A468 ML17333A470
References
AEP:NRC:0969AM, AEP:NRC:969AM, NUDOCS 9606200158
Download: ML17333A468 (15)

Text

CATEGORY 1 REGULA ~ INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9606200158 DOC.DATE: 96/06/12 NOTARIZED: NO DOCKET ¹ FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E.E American Electric Power Co., Inc.

RECIP.NAME RECIPIENT AFFILIATION

. Document Control Branch (Document Control Desk)

SUBJECT:

Provides third 10-yr interval in-service pump test plan 6 requests relief from ASME Section XI requirements.

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:

TITLE; OR Submittal: Inservice/Testing/Relief from ASME Code GL-89-04 NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL' ID CODE/NAME LTTR ENCL PD3-1 LA 1 PD3-1 PD 1 1 HICKMANgJ 1 1 INTERNAL: AEOD/SPD/RAB 1 1 ILE CENTE 01 1 1 NRR/DE/ECGB 1 1 /D~EMCB 1' NRR/DE/EMEB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 RES/DET/EMMEB 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC 1 1 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

DOCUMENT CONTROL DESK, PLEASE HELP US TO REDUCE WASTE! CONTACT THE ROOM OWFN 5D-5(EXT. 415-2083) TO EI IMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU 'DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 14

American Electrl .r 1 Riverside Plaza Columbus, OH 4321 5 2373

/f P. 614 223 1000 AINMICQM KI.KCTHEC PQWKR June 12, 1996 AEP: NRC: 0969AM Docket Nos.: 50-315 50-316 U, S, Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:

Donald C. Cook Nuclear Plant Units 1 and 2 RELIEF REQUESTS FOR THE THIRD TEN-YEAR PUMP IN-SERVICE TEST PLAN The purpose of this letter is to provide the NRC with a copy of the Donald C. Cook Nuclear Plant's third ten year interval in-service pump test plan, and t:o request relief from ASME Section XI requirements which have been determined to be impractical to meet.

Attachment 1 contains the relief requests and attachment 2 contains the third ten-year interval in-service pump test plan.

The current in-service pump test program will expire on June 30, 1996. The attached relief requests are being submitted in accordance with 10 CFR 50.55a(f)(5)(iv). This regulation requires that, when the revised in-service test program does not include an ASME Code requirement, the licensee demonstrate to the NRC the impracticality of those requirements within twelve months of the expiration of the current program. We, therefore, request approval of the relief requests by June 30, 1997.

Sincerely, E. E. Fitzpatrick Vice President llg Attachments 200038 CC: A. A. Blind C. Charnoff H. J. Miller NFEM Section Chief NRC Resident Inspector - Bridgman PCX7I l J. R. Padgett I

9sosaooiss 9sosm 5't PDR ADQCK 05000$ f P PDR~I

U. S. Nuclear Regulatory Commission AEP:NRC: 0969AM Page 2 bcc: S. J. Brewer/D. H. Malin/M. S. Ackerman/R. G. Vasey D. F. Powell J. D. Benes J. A. Kobyra/S. H. Steinhart/S. P. Hodge J. B. Shinnock J. S. Wiebe J. B. Hickman, NRC - Washington, D. C. w/attachment P, G. Schoepf/F. R. Pisarsky PRONET w/attachment DC-N-6015.1

ATTACHMENT 1 TO AEP:NRC:0969AM IN-SERVICE PUMP TEST PLAN RELIEF REQUESTS

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S Attachment 1 to AEP:NRC: 09 Page 1 COOK NUCLEAR PLANT,PUMP IST PROGRAM RELIEF REQUEST NO. 1 TITLE: Containment S ra Pum Vibration Limits O General O Specific X

Unit Applicability: 1 2 X 1 and 2 PUMP NAME: Containment S ra PUMP NUMBER(S): PP-009 SYSTEM: Containment S ra CTS FLOW DIAGRAM: 5144 ASME CLASS: 2 PUHP FUNCTION: Provide cool water flow to s ra the containment atmos here in a LOCA or steamline break.

RELIEF TYPE O X COMPLIANCE WITH CODE REQUIREMENTS ASME CODE TEST REQUIREMENT

REFERENCE:

IS IHPRACTICAL OMa-1988, Part 6, Table 3a Ranges for vibration'est parameters CODE REQUIREMENT DESCRIPTION: (for centrifugal pumps >600 rpm)

Acceptable range <2.5 vibration reference value (V)

Alert range >2.5 V to 6 V or >0.325 in/sec Required action range >6 V or >0.70 in/sec BASIS THAT COMPLIANCE WITH CODE REQUIREMENTS IS IMPRACTICAL:

The design of the CTS pumps utilizes a four vane impeller in a double volute casing. This combination of an impeller with an even number of vanes operating in a casing with two volutes creates a high, reinf'orced vibration response at the vane passing frequency (7200 cpm). This condition is further compounded by the fact that the quarterly IST tests are performed at only 25K of the pump's design flow. This results in the discharge angle of the impeller flow not matching the stationary volute angle, producing high interaction forces between the impeller and the volutes. This high vane pass frequency amplitude is the major component......

of overall amplitude and is not indicative of overall pump condition. On this basis, compliance with the referenced acceptance criteria would be impractical due to the burden created by unnecessary repair and replacement of otherwise suitable pump components.

PROPOSED ALTERNATE TESTING:

Acceptable range <2.0 V Alert range >2.0 V to 4.0 V or 1.2 in/sec Required action range >4 V or 2.0 in/sec BASIS ALTERNATE TESTING YIELDS ACCEPTABLE LEVELS OF QUALITY AND SAFETY:

Although the overall vibration amplitude is increased over the alert and required action limits of ASME OMa-:1988. Part 6. Table 3a, the proposed alternate values are based upon our review of past operating data for these pumps. The values are a more representative basis for trending performance of the containment spray um s, and as such rovide an acce table level of uality and safety.

to AEP:NRC:0969 Page 2 COOK NUCLEAR PLANT PUMP IST PROGRAM RELIEF REQUEST NO. 2 TITLE: Boric Acid Transfer Pum Axial Vibr ation Measurement Unit Applicability: 1 2 X 1 and 2 PUMP NAME: Boric Acid Transfer Pum PUMP NUMBER(S): 1-PP-45-1 2'-PP-46-3 4 SYSTEM: CVCS-Makeu FLOW DIAGRAM: 12-5131 ASHE CLASS: 2 PUMP FUNCTION: Transfer boric acid solution from stora e tank to char in um suction header.

RELIEF TYPE ASME CODE TEST REQUIREMENT

REFERENCE:

OMa-1988, Part 6, Paragraph 4.6.4(a)

CODE REQUIREMENT DESCRIPTION:

On centrifugal pumps, measurements shall be taken in a plane approximately perpendicular to the rotating shaft in two orthogonal directions on each accessible pump bearing housing. Measurement also shall be taken in the axial direction on each accessible pump thrust bearing housing.

BASIS THAT COMPLIANCE WITH CODE REQUIREMENTS IS IMPRACTICAL:

The pump thrust bearing housing is inaccessible. It is very close to the coupling, and safety considerations prevent placement of the probe. In addition, the housing is partially blocked by the impeller adjustment nuts.

PROPOSED ALTERNATE TESTING:

Take measurements in a plane approximately perpendicular to the shaft in two orthogonal directions on each accessible pump bearing housing.

BASIS ALTERNATE TESTING YIELDS ACCEPTABLE LEVELS OF QUALITY AND SAFETY:

Measurements taken in planes perpendicular to the shaft in two orthogonal directions have provided adequate data to evaluate pump performance and condition.

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~ t Attachment 1 to AEP:NRC:0969~ Page 3 COOK NUCLEAR PL'ANT PUMP IST PROGRAM RELIEF REQUEST NO. 3 TITLE: Su ersede OMa-1988 Corrective Action Part 6 Para ra h 6.1 X

Unit Applicability:

Gener al D Specific 1 2 X 1 and 2 PUMP NAME:Various PUMP NUMBER(S):PP-03 07 46 26 09 -31 T-106 -130 SYSTEM:All IST Pum in S stems in Table A FLOW DIAGRAM:See Table A ASHE CLASS:253 PUMP FUNCTION: As listed in Table A RELIEF TYPE O X COMPLIANCE WITH CODE REQUIREMENTS IS IMPRACTICAL ASME CODE TEST REQUIREMENT

REFERENCE:

OMa-1988, Part 6, Subsection 6. 1 Acceptance Criteria CODE REQUIREMENT DESCRIPTION:

OMa-1988, Part 6, Subsection 6. 1, First Paragraphs Second Sentence Relative to Action Range. If deviations fall within the requi red action range of Table 3. the pump shall be declared inoperable unti 1 the cause of the deviation has been determined and the condition corrected.

BASIS THAT COMPLIANCE WITH CODE REQUIREMENTS IS IMPRACTICAL:

Compliance with the required acceptance criteria will impose a significant burden if test data cannot be analyzed to determine if a pump is still capable of performing its safety function. Past experience evaluating pump test data clearly indicates a burden will be created by unnecessary extension of Technical Specification LCO durations. unnecessary reportabi lity submittals, unnecessary repairs and replacements of otherwise suitable equipment, and unnecessary component wear due to accelerated testing frequencies.

PROPOSED ALTERNATE TESTING:

ON-1995, Subsection ISTB 6.2.2. Action Range. If the measured test parameter values fall within the requi red action range of Table ISTB 5.2. 1-1 or Table ISTB .

5.2.1-2. as applicable, the pump shall be declared inoperable until either the cause of the deviation has been determined and the condition is corrected, or an analysis of the pump is performed and new reference values are established in accordance with paragraph ISTB 4.6.

to AEP:NRC:0969 Page 4 BASIS ALTERNATE TESTING YIELDS ACCEPTABLE LEVELS OF QUALITY AND SAFETY't is requested that the corrective action requirements, per ASME OMa-1988, Part 6, Subsection 6.1, be superseded for all pumps included in the ZST program. The proposed alternative is to follow subsection ZSTB 6.2.2 of ASME OM-1995, "Action Range." When applying the requirements of ISTB,6.2.2, Tables 5.2.1-1 and ISTB 5.2.1-2, the Group A test hydraulic acceptance criteria will be used since all pumps are treated as Group A pumps by ASME OMa-1988.

The current pump IST program trends the test results and replaces the pumps as they approach the IST lower limits. The trending allows for evaluations of system conditions if the test point deviates from the trend path. At that time, the pump is retested or the system conditions are reviewed to determine the cause of the deviation. This type of evaluation is consistent with the current code and is consistent with the 1995 code. On this basis, we are requesting that the corrective actions be established per ASME OM-'1995 requirements since the OMa-1988 code does not allow evaluation of test conditions.

to AEP:NRC:0969AM DONALD C. COOK NUCLEAR PLANT - UNI'I' Page 5 PUMP INSERVICE TEST PROGRAM TABLE A PROGRAM

SUMMARY

TEST PARAMETERSr Discharge Differential Flow Vibration Pump Speed Pressure Pressure Rate Amplitude Test Pump Service Number (N) (P) (~P) (Q) (V) Frequency (Drawing No.)

Auxiliary Feedwater

• PP-3W No No Yes Yes Yes Quarterly (I-5106A) PP-3E No No Yes Yes Yes Quarterly PP-4 Yes No Yes Ycs Ycs Quarterly Essential Service Water PP-7W No No Yes Yes Yes Quarterly (1-5113) PP-7E No No Yes Yes Yes Quarterly Centrifugal Charging PP-50W No No Yes Yes Yes Quarterly (1-5129) PP-50E No No Yes Yes Yes Quarterly Boric Acid Transfer PP-46-1 No No Yes Yes Quarterly (12-5131) PP-46-2 No No Yes Yes Yes'es'es Quarterly Component Cooling Water PP-10W No No Yes Yes Quarterly (I-5135A) PP-10E No No Yes Yes Yes Quarterly Safety Injection PP-26N No No Yes Yes Yes Quarterly

'1-5142)

PP-26S No No Yes Yes Yes Quarterly Residual I-leat Removal PP-35W No No Yes Yes Yes Quarterly

'1-5143)

PP-35E No No Yes Yes Yes Quarterly to AEP:NRCr0969AH Page 6 DONALD C. COOK NUCLEAR PLANT - UN1T 1 PUMP INSERVICE TEST PROGRAM TABLE A PROGRAM

SUMMARY

TEST PARAMETERS'ump Discharge Differential Flow Vibration Service Pump Speed Pressure Pressure Rate Amplitude Test (Drawing No.) Number (N) (P) (IP) (Q) (V) Frequency Containment Spray PP-9W No No Yes Yes Quarterly

'1-5144)

PP-9E No No Yes Yes Yes'es'es Quarterly Diesel Fuel Oil QT-106-AB1 No Yes No Yes Quarterly Transfer QT-106-AB2 No Yes No Yes Yes Quarterly

'1-5151A 8c C) QT-106-CD 1 No Yes No Yes Yes Quarterly QT-106-CD2 No Yes No Yes Yes Quarterly Spent Fuel Pit Cooling 12-PP-3 1N No No Yes Yes Yes Quarterly (12-5136)~

Jacket Water QT-130-AB1 No No Yes Yes Yes Quarterly (1-5151B Ec D) QT-130-AB2 No No Yes Yes Yes Quarterly QT-130-CD1 No No Yes Yes Yes Quarterly QT-130-CD2 No No Yes Yes Yes Quarterly These pumps are tested on test, bypass, or minimum flow loops per ASME OMA-1988 Part 6, g 3.2.

Refer to Comment l.

Refer to Comment 2.

Refer to Code Relief Request l.

Refer to Code Relief Request 2.

Refer to Code Relief Request 3.

Only North Spent Fuel Pit Pump shown here due to the alignment of its cooling train to Unit 1 Component Cooling Water.

V'ONALD to AEP:NRCr0969AM Page 7 C. COOK NUCLEAR PLANT - UNIT 2

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PUMP INSERVICE TEST PROGRAM TABLE A PROGRAM

SUMMARY

TEST PARAMETERS'ifferential Discharge Flow Vibration Pump Speed Pressure Pressure Rate Amplitude Test Pump Service Number (N) (P) (AP) (Q) (V) Frequency (Drawing No.)

Auxiliary Feedwater PP-3W No No Yes Yes Yes Quarterly ~

'2-5106A)

PP-3E No No Yes Yes Yes Quarterly PP-4 Yes No Yes Yes Yes Quarterly Essential Service Water PP-7W No No Yes Yes Yes Quarterly (2-5113) PP-7E No No Yes Yes Yes Quarterly Centrifugal Charging PP-50W No No Yes Yes Yes Quarterly (2-5129) PP-50E No No Yes Yes Yes Quarterly Boric Acid Transfer PP-46-3 No No Yes Yes Quarterly (12-5131) PP-46-4 No No Yes Yes Yes'es'es Quarterly Component Cooling Water PP-10W No No Yes Yes Quarterly (2-5135A) PP-10E No No Ycs Yes Yes Quarterly Safety Injection '2 PP-26N No No Yes Yes Yes Quarterly

-5142) PP-26S No No Yes Yes Yes Quarterly Residual Heat Removal PP-35W No No Yes Yes Yes Quarterly

'2-5143)

PP-35E No No Yes Yes Yes Quarterly to AEP:NRCt0969AM Page 8 DONALD C. COOK NUCLEAR PLANT - UNIT 2 PUMP INSERVICE TEST PROGRAM TABLE A PROGRAM

SUMMARY

TEST PARAMETERS Discharge Differential Flow Vibration Pump Service Pump Speed Pressure Pressure Rate Amplitude Test (Drawing No.) Number (N) (P) (h,P) (Q) (V) Frequency Containment Spray PP-9W No No Yes Yes Yes~ Quarterly

'2-5144)

PP-9E No No Yes Yes Yes4 Quarterly Diesel Fuel Oil QT-106-AB1 No Yes No Yes Yes Quarterly Transfer QT-106-AB2 No Yes No Yes Yes Quarterly

'2-5151A

& C) QT-106-CD1 No Yes No Yes Yes Quarterly QT-106-CD2 No Yes No Yes Yes Quarterly Spent Fuel Pit Cooling 12-PP-31S No No Yes Yes Yes Quarterly

( 2-5136)c 1

Jacket Water QT-130-AB1 No No Yes Yes Yes Quarterly (2-51518 & D) QT-130-AB2 No No Yes Yes Yes Quarterly QT-130-CD1 No No Yes Yes Yes Quarterly QT-130-CD2 No No Yes Yes Yes Quarterly These pumps are tested on test, bypass, or minimum flow loops per ASME OMA-1988 Part 6, $ 3.2.

Refer to Comment 1.

Refer to Comment 2.

Refer to Code Relief Request 1.

Refer to Code Relief Request 2.

f Refer to Code Relief Request 3.

g Only South Spent Fuel Pit Pump shown here due to the alignment of its cooling train to Unit 2 Component Cooling Water.