ML17321A618
| ML17321A618 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/10/1985 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0730G, AEP:NRC:730G, NUDOCS 8505160134 | |
| Download: ML17321A618 (16) | |
Text
SUBJECT:
Responds to DL. bliggjnton 850326 ltr,Relief requested from Section XI of ASME Boiler tt Pressure Vessel Code: for certa.in valve 8 testing requirements,Rev 1 to valve summary sheets for inservice testing program encl'ISTRIBUTION CODE!
A007D COPIES RECEIVED:LTR ENCL SIZE;- '~ E)W TITLE; OR Submittal: Inservice Inspection/Testing NOTES: >~ 0<~+1~>
OL: 10/25/7(I 05090315 05000316 OL: 12/23/72 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSIO~N NSN:8505100150 ~ DOC ~ DATE: 85/05/10 NOTAiED:
NO DOCKET FACIL:50 315 Donald C.
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05000315 50-316 Donald c, cook Nuclear Power PlantE Uni.t 2E Indiana 8
05000316 AUTH ~ NAME.
AUTHOR AFFILIATION ALEXICH<M,P, Indiana L Michigan Electric Co, RECIP ~ NAME" RECIPIENT AFFILIATION DENTONEH ~ R ~
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I INDIANA8 NICHIGAN ELECTRIC COlMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 May 10, 1985 AEP:NRC:0730G Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 INSERVICE TESTING PROGRAM-CODE RELIEFS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Reference:
1)
Letter from Mr. David L. Wigginton, NRC, dated March 26, 1985 2)
Our Letter No. AEP:NRC:0730F dated May 10, 1985
Dear Mr. Denton:
This letter and its Attachments are in response to the above referenced letter from Mr. D. L. Wigginton of your staff and provide the revised pages for the Inservice Testing Program (IST) for the Donald C.
Cook Nuclear Plant.
This submittal is made pursuant to 10 CFR Section 50.55a(g)(6)(i) and requests code relief from sec'tion XI of the ASME Boiler and Pressure Vessel Code for certain valve and pump testing requirements.
Attachment 1 to this letter is a complete revision to the IST Pump Program for the D. C.
Cook Nuclear Plant.
The code relief requests discussed at the March 6 and 7, 1985 meeting between our staff and the NRC are detailed in Tables B,
D and E.
Attachments 2 and 3 contain the request for code relief for the valve testing programs for Units 1 and 2 respectively.
For your convenience these attachments are submitted as revised pages to the IST Valve Program which was submitted in our earlier letter AEP:NRC:0730C dated'October 2, 1984.
For your information those code reliefs which were discussed at the March meeting are marked as "C-1" in the margin.
In addition, the revised pages include valve program changes that were agreed upon between the NRC and our staff at that meeting.
These revisions are marked as "M-1" in the margin.
Other changes identified by us during the preparation of this submittal, which are either minor or editorial in
- nature, are marked as "E-1".
Attachments 1,
2 and 3 replace the corresponding pages of the IST program submitted in our earlier letter no.
AEP:NRC:0730C dated October 2, 1984.
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Mr. Harold R.
Den AEP:NRC:0730G This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, M. P.
A xich Vice Presiden Attachments cc:
John E. Dolan (w/o attachment)
W. G. Smith, Jr. - Bridgman (w/attachment)
R.
C. Callen (w/o attachment)
G. Bruchmann (w/o attachment.)
G. Charnoff (w/o attachment)
NRC Resident Inspector Bridgman (w/attachment)
R. Lyon EGGG
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ATTACHMENT NO.
1 TO AEP:NRC:0730G
ATI'ACHMENT,NO. 1 AEP:NRC: 0730G DONALD C.
COOK NUCLEAR PLANT UNXTS NO.
1 AND 2 ASYiE B
& PV CODE SECTXOH XX A.
The pump test program shall be conducted with Subsection XNP of Section XX of the the ASYiE Boiler and Pressure Vessel Code 1975 Addenda, except for specific relief accordance with 10 CFR 50.55a(g)(5)(iii) identified in in accordance 1974 Edition of through Summer" requested in which is B.
The period for which the pump inservice test program is applicable is the period beginning December 23, 1978 for Unit 1 and the period beginning July 1, 1978 for Unit 2.
C. 'he pump test program was developed employing the classification guidelines contained in Regulatory Guide 1.26, Revision 2 for Quality, Groups B and C,
and the definition of the reactor coolant system boundary contained in 10 CFR 50.2 (v) for Group A.
(Quality Groups A, 13, and C are the same as ASHE Class 1, 2, and 3, respectively)
Using these guidelines and XNP-1100, the pump list attached as Table A was developed.
Table A
identifies the following:
- i. The pump number and service it performs along with the drawing identification number on which it is found+
ii. The applicable test parameters:
2.
Speed inlet Pressure 3-4 ~
5.
6.
Differential Pressure Determined as the difference. between measured discharge and suction pressures Flow Rate Vibration Amplitude Bearing Temperature iii. The test frequency required.
Page 1 of 7 Revision 3
5/1/85
DONALD C.
COOI< NUCLEAR PLANT UNITS NO 1
AND 2 PUIIP INSHRVICE TEST PROGRAI'1 PROGRAh1 SUhlIIARY PUIip SERVICE DNG NO.
PUIIP NUhIBER S
INLET DIFFERENTIAL FLON VIBRATION BEARING TEST SPEED PRESSURE PRESSURE RATE AhiPLITUBE TEMPERATURE FREQUENCY N
P
~
P Q
V (4)
T (1)
AUXILIARY FHEDNATER 0
ESSENTIAL SERVICE CENTRIFUGAL CHARGING PP-31'3 PP-3E PP-4 PP-7N PP-7E PP-50N PP.-50E 130 NO YES NO NO NO NO YES YES YHS YES YES YHS YES (3)
(3)
YES YHS Y e, YES YES YHS YES YES*
YES*
YES YES NO**
NO**
YES YES YES YES YES YES YES hIONTEILY YES NONTHLY YES (5)
IIONTHLY YES (5)
HONTHLY YES IIONTHLY YES I10NTHLY BORIC ACID TRANSFER (5131)
PP-46-1 PP-46-2 PP-46-3 NO NO NO YES YES YES (3)
(3)
(3).
YES YES YES NO*
NO*
NO*
YES YHS YES YES YES YES IIONTEILY hIONTHLY IIONTkjLY COliPONENT COOLING 5
5 SAFETY INJECTIOI3 PP-10'P-10E PP-26N PP-26S NO NO NO I%TO YHS YHS YHS YES YES YES YES YES YES YES YES YES NO**
YES NO**
YES YES YES YES YES hiONTHLY NONTHLY I10NTEILY ViOHTHLY RESIDUAL PP-351'3 HEAT REliOVAL PP-35E CONTAIN11ENT PP-9h DIESEL FUEL OIL QT-106 ABl TRANSFER PUhIPS QT-106 AB2 (5151)
QT-106 CDl C
NO I30 NO N
NO NO NO NO YES YES YES YHS YHS YHS YES YES*
YES YES 'ES*
YES YES YES*
YES YES YES (6)
YES YES YES (6)
YES YES YES (6)
YES Y
YES YES YES NO (5)
NO (5)
NO (5)
HOIiTHLY I10NTHLY I10NTHLY QUARTERLY (2 QUARTERLY (2 QUARTERLY
( 2 A
~
(2 (1) Bearing Temperature vill be measured annually per Section XI Code Subarticle IMP 3300, except for the Diesel Fuel Oil Transfer Pumps.
(2) Refer to TABLE B.
(3) Inlet Pressure lieasurement is in Head of Liquid.
(4) Refer to TABLE C.
ATZACHMEh3T NO.
1 (5) Refer to TABLE D.
AHP:NRC:0730G (6) Refer to TABLE E Page 2 of 7 Revision 3 5/1/85
DONALD C ~
COOI<
NUCLEAR PLANT UNITS NO.
1 AND 2 PUt)P INSERVICE TEST PROGRAH
~TABL, (CONTINUED)
PROGRAh SUI1ViARY
- Pumps are tested on by-pass (test) loops since it is impractical to test in regular circuits-per Section XI Code Subarticle It'IP 1400
- Pumps are tested on recirculation (minimum flow) paths to prevent unsafe operating conditions (impractical to align system for full flow test) per Section XI Code Subarticle lNP 1400
~ 0 C) 4J P Q
~
Page 3 of 7 Revision 3
5/1/85
ATTACHMENT NO. l AEP:NRC: 0730G DONALD C.
COOK NUCLEAR PLANT UNITS NO. l AND 2 PUNP INSERVICE TEST PROGRAN
~LE 8 CODE RELIEF REQUEST Request that frequency of testing for the Diesel Fuel Oil Transfer Pumps be established on a quarterly basis.
Operation of both pumps during a monthly test is restricted by the limited capacity of the diesel generator fuel oil day tank.
Two pump testing will cause excessive and unnecessary operation of the emergency diesel generators in order to keep the level in the tank from overflowing.
Constant draining of the tank to maintain tank level without running the diesel generators is a potential fire and utility hazard.
A potential for overflowing the tank is present in either case.
Single pump testing will be conducted during monthly emer-gency diesel generator operation.
Each pump will be tested on a staggered basis (every other month) during a quarterly period.
- Note:
This quarterly test frequency is in accordance with the l980 Edition of Section XI, Subarticle IPlP-3400
'age 4 of 7 Revision 3
5/l/85
ATTACHMENT NO.
1 AEP:NRC: 0730G DONALD C COOK NUCLEAR PLANT-UNITS NO.
1 AND 2 PUMP INSERVICE TEST PROGRAll
~~~E CODE RELIEF REQUEST Request that vibration amplitude, as specified in Section XI Subarticle INP-4510, be measured in terms of velocity, inches per second peak instead of peak to peak displacement.
The major characteristics of vibration are displacement and fre-quency.
Velocity provides a better indication of vibration severity because it includes both displacement and the frequency of displace-ment.
Since velocity is directly related to displacement, the velocity acceptance criteria for vibration amplitude is consistant to the acceptance criteria for displacement as specified in Table IllP 3100-2.
page 5 of 7 Revision 3
5/1/85
AITACEGWZ NO.
1 AEP:NRC: 0730G DONALD C.
COOK NUCLEAR PLANT UNXTS NO.
1 AND 2 PU51P INSERVICE TEST PROGRAjj TLBL1~
CODE RELIEF REQUEST a.
Request that the pump bearing temperature requirements, per Section XI Subarticle INP-4310, be amended for the Essential Service Water Pumps.
Except for one bearing assembly located within the motor
- stand, the remaining shaft bearings are located below the main pump flange and are inaccessible.
In addition to measuring the pump bearing, temperatures will be measured on the motor bearing blocks.
b.
Request that the Diesel Fuel Oil Transfer Pumps be exempt from bearing temperature requirements as stated Section XX Subarticle INP-3300.
The inboard and outboard sleeve bearings on these 2
HP gear pumps are lubricated and cooled by the pumped fluid.
Temp-erature readings are therefore inconclusive since bearing measurement points are not responsive to the changes in bearing temperature.
Bearing problems on gear pumps can be more readily identified by degradation of pump capacity.
Flow rate deterioration indicates the existence of excessive clearances due to bear-ing wear and problems.
In addition, the code required pump running time for yearly bearing temperature measurement can not be met due to the limited capacity of the diesel generator fuel oil day tank.
Page 6 of 7 Revision 3
5/1/85
ATTACHMEFZ NO. 1 AEP:NRC: 0730G DONALD C.
COOK NUCLEAR PLANT. UNITS NO.
1 AND 2 PUHP INSERVICH TEST PROGRAjl
~BLE E
CODE RELIEF REQUEST Request that the duration of pump operation for testing, per Section XI Subarticle INP-3500, be amended for the Diesel Fuel Oil Transfer Pumps.
These pumps supply the diesel generator fuel oil day tank.
A conservative level is maintained in the tank to meet the minimum capacity per Technical Specification requirements.
Due to the limited capacity of this tank, the pump operating test range is restricted.
It is requested to record test parameters immediately after pump operation has stabil-ized.
Page 7 of 7 Revision 3
5/1/85
I