ML17333A468
| 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: |
| References | |
| AEP:NRC:0969AM, AEP:NRC:969AM, NUDOCS 9606200158 | |
| Download: ML17333A468 (15) | |
Text
CATEGORY 1
REGULA
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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 ID CODE/NAME PD3-1 LA HICKMANgJ INTERNAL: AEOD/SPD/RAB NRR/DE/ECGB NRR/DE/EMEB OGC/HDS2 RES/DSIR/EIB EXTERNAL: LITCO ANDERSON NRC PDR COPIES LTTR ENCL' 1
1 1
1 1
1 1
1 1
1 0
1 1
1 1
1 1
RECIPIENT ID CODE/NAME PD3-1 PD ILE CENTE 01
/D~EMCB NUDOCS-ABSTRACT RES/DET/EMMEB NOAC COPIES LTTR ENCL 1
1 1
1 1'
1 1
1 1
1 1
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, 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
/f P.
American Electrl
.r 1 Riverside Plaza Columbus, OH 4321 5 2373 614 223 1000 June 12, 1996 Docket Nos.:
50-315 50-316 AINMICQM KI.KCTHEC PQWKR AEP: NRC: 0969AM 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 J.
R. Padgett PCX7I l I
9sosaooiss 9sosm PDR ADQCK 05000$ f5't P
PDR~I
U. S. Nuclear Regulatory Commission Page 2
AEP:NRC:
0969AM 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 Unit Applicability:
1 PUMP NAME:
Containment S ra O
X Specific 2
X 1 and 2 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 IS IHPRACTICAL ASME CODE TEST REQUIREMENT
REFERENCE:
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.
Attachment 1 to AEP:NRC:0969 Page 2
COOK NUCLEAR PLANT PUMP IST PROGRAM RELIEF REQUEST NO.
2 TITLE:
Boric Acid Transfer Pum Axial Vibration Measurement Unit Applicability:
1 PUMP NAME:
Boric Acid Transfer Pum 2
X 1 and 2
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
Gener al Unit Applicability:
1 PUMP NAME:Various PUMP NUMBER(S):PP-03 -04 SYSTEM:All IST Pum in S stems in Table A
PUMP FUNCTION:
As listed in Table A
DSpecific 2
X 1 and 2 50 10 35 31 T-106 -130 FLOW DIAGRAM:See Table A
ASHE CLASS:253 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.
Attachment 1 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.
Attachment 1 to AEP:NRC:0969AM DONALDC. COOK NUCLEARPLANT-UNI'I' PUMP INSERVICE TEST PROGRAM TABLEA PROGRAM
SUMMARY
Page 5
Pump Service (Drawing No.)
AuxiliaryFeedwater *
(I-5106A)
Essential Service Water (1-5113)
Centrifugal Charging (1-5129)
Boric Acid Transfer (12-5131)
Component Cooling Water (I-5135A)
Safety Injection
'1-5142)
Residual I-leat Removal
'1-5143)
Pump Number PP-3W PP-3E PP-4 PP-7W PP-7E PP-50W PP-50E PP-46-1 PP-46-2 PP-10W PP-10E PP-26N PP-26S PP-35W PP-35E Speed (N)
No No Yes No No No No No No No No No No No No Discharge Pressure (P)
No No No No No No No No No No No No No No No TEST PARAMETERSr Differential Pressure
(~P)
Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Flow Rate (Q)
Yes Yes Ycs Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Vibration Amplitude (V)
Yes Yes Ycs Yes Yes Yes Yes Yes'es'es Yes Yes Yes Yes Yes Test Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly
Attachment 1 to AEP:NRCr0969AH DONALDC. COOK NUCLEARPLANT-UN1T 1 PUMP INSERVICE TEST PROGRAM TABLEA PROGRAM
SUMMARY
Page 6
TEST PARAMETERS'ump Service (Drawing No.)
'1-5144)
Diesel Fuel Oil Transfer
'1-5151A8c C)
Spent Fuel Pit Cooling (12-5136)~
Jacket Water (1-5151B Ec D)
Pump Number PP-9W PP-9E QT-106-AB1 QT-106-AB2 QT-106-CD 1 QT-106-CD2 12-PP-3 1N QT-130-AB1 QT-130-AB2 QT-130-CD1 QT-130-CD2 Speed (N)
No No No No No No No No No No No Discharge Pressure (P)
No No Yes Yes Yes Yes No No No No No Differential Pressure (IP)
Yes Yes No No No No Yes Yes Yes Yes Yes Flow Rate (Q)
Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Vibration Amplitude (V)
Yes'es'es Yes Yes Yes Yes Yes Yes Yes Yes Test Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly 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 ofits cooling train to Unit 1 Component Cooling Water.
Attachment 1 to AEP:NRCr0969AM Page 7
~ ~V'ONALD C. COOK NUCLEARPLANT-UNIT2 PUMP INSERVICE TEST PROGRAM TABLEA PROGRAM
SUMMARY
Pump Service (Drawing No.)
AuxiliaryFeedwater
'2-5106A)
Essential Service Water (2-5113)
Centrifugal Charging (2-5129)
Boric Acid Transfer (12-5131)
Component Cooling Water (2-5135A)
Safety Injection
'2
-5142)
'2-5143)
Pump Number PP-3W PP-3E PP-4 PP-7W PP-7E PP-50W PP-50E PP-46-3 PP-46-4 PP-10W PP-10E PP-26N PP-26S PP-35W PP-35E Speed (N)
No No Yes No No No No No No No No No No No No Discharge Pressure (P)
No No No No No No No No No No No No No No No TEST PARAMETERS'ifferential Pressure (AP)
Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Ycs Yes Yes Yes Yes Flow Rate (Q)
Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Vibration Amplitude (V)
Yes Yes Yes Yes Yes Yes Yes Yes'es'es Yes Yes Yes Yes Yes Test Frequency Quarterly
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Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly
Attachment 1 to AEP:NRCt0969AM Page 8
DONALDC. COOK NUCLEARPLANT-UNIT2 PUMP INSERVICE TEST PROGRAM TABLEA PROGRAM
SUMMARY
Pump Service (Drawing No.)
'2-5144)
Diesel Fuel Oil Transfer
'2-5151A&C)
Spent Fuel Pit Cooling
( 1 2-5136)c Jacket Water (2-51518 & D)
Pump Number PP-9W PP-9E QT-106-AB1 QT-106-AB2 QT-106-CD1 QT-106-CD2 12-PP-31S QT-130-AB1 QT-130-AB2 QT-130-CD1 QT-130-CD2 Speed (N)
No No No No No No No No No No No Discharge Pressure (P)
No No Yes Yes Yes Yes No No No No No TEST PARAMETERS Differential Pressure (h,P)
Yes Yes No No No No Yes Yes Yes Yes Yes Flow Rate (Q)
Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Vibration Amplitude (V)
Yes~
Yes4 Yes Yes Yes Yes Yes Yes Yes Yes Yes Test Frequency Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly f
g 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.
Refer to Code Relief Request 3.
Only South Spent Fuel Pit Pump shown here due to the alignment ofits cooling train to Unit 2 Component Cooling Water.