ML17334B355
| ML17334B355 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/05/1990 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17334B354 | List: |
| References | |
| AEP:NRC:0969R, AEP:NRC:969R, PROC-900205, NUDOCS 9003090178 | |
| Download: ML17334B355 (22) | |
Text
ATTACHMENT 1 TO AEP:NRC:0969R DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 INSERVICE TESTING PUMP PROGRAM REVISION 2 90OSO90i7S 90O2ie PDR ADOCK 050003i5 P PNU
0 DONALD C. COOK NUCLEAR PLANT - UNITS NO. 1 AND 2 ASME B & PV CODE SECTION XI Pump Inservice Test Program A. The pump test program shall be conducted in accordance with Section XI, Subsection IWP of the 1983 Edition of the ASME Boiler and Pressure Vessel Code through Summer 1983 Addenda, except for specific code relief, requested in accordance with 10 CFR 50.55a(g)(5)(iii). Exemptions or ammendments are identified in Code Relief Requests I and II.
B. This pump test program is for the 2nd ten year inspection/test interval commencing July 1, 1986 for both Unit 1 and Unit 2.
C. The 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, B, and C are the same as ASME Class 1, 2, and 3, respectively). Using these guidelines and IWP-1100, the pump list attached as Table A was developed.
Table A identifies the following:
- i. The pump number and service it performs along identification number on which't is found.
with the drawing ii. The applicable test parameters:
Speed
- 2. Inlet Pressure
- 3. Differential Pressure - determined as the difference between measured discharge and suction pressures
- 4. Flow Rate 5 ~ Vibration Amplitude
- 6. Bearing Temperature iii. The test frequency required.
Revision 2 Page 1 of 5 2/5/90
0 C
DONALD C. COOK NUCLE T - UNITS NO. 1 AND 2 PUHP INSER E TEST PROGRAM TABLE A PROGRAM SUHHARY TEST PARAMETERS Pump Inlet Differential Flow Vibration c Service Bearing Test Pump Speed Pressure Pressure Rate Amplitude Temperature Frequency (Drawing No.) Number N P. DP V 1 Tb (1)
Auxiliary PP--3W No Yes Yes Yes Yes Yes Quarterly Feedwater PP-3E No Yes Yes (5106A) PP-4 Yes Yes Yes Quarterly Yes Yes 'es Yes Yes Yes Quarterly Essential b PP-7W No Yes Yes Yes Yes Yes Quarterly Service PP-7E No Yes Yes Water (5113)
Yes Yes Yes Quarterly Centrifugal PP-50W No Yes Yes Yes Yes Yes Quarterly Charging PP-50E No Yes Yes Yes Yes Yes Quarterly.
(5129)
Boric Acidb PP-46-1 No Yes Yes Yes Yes Yes Quarterly Transfer PP-46-2 No Yes Yes Yes Yes Yes Quarterly (5131) PP-46-3 No Yes Yes Yes Yes Yes Quarterly PP-46-4 No Yes Yes Yes Yes Yes Quarterly Component PP-10W No Yes Yes Cooling Yes Yes Yes Quarterly PP-10E No Yes Yes Yes Yes Yes Quarterly Water (5135A)
Safety a PP-26N No Yes Yes Yes Yes Yes Quarterly Inj ection PP-26S No Yes Yes Yes Yes Yes Quarterly (5142)
Residual a PP-35W No Yes Yes Yes Yes Yes Quarterly Heat Removal PP-35E No Yes Yes (5143)
Yes Yes Yes Quarterly Revision 2 Page 2 of 5 2/5/90
ST PARAMETERS Pump Inlet Differential Flow Vibration Bearing c Test Service Pump Speed Pressure Pressure Rate Amplitude Temperature Frequency (Drawing No.) Number N P. DP Q V Tb (1) l.
Containment a PP-9W No Yes Yes Yes Yes Yes Quarterly Spray (5144) PP-9E No Yes Yes Yes Yes Yes Quarterly Diesel Fuel QT-106-AB1 No Yes Yes Yes (2) Yes No (1) Quarterly Oil Transfer QT-106-AB2 No Yes . Yes Yes (2) Yes No (1} Quarterly (5151) QT-106-CD1 No Yes Yes Yes (2) Yes No (1) Quarterly QT-106-CD2 No Yes Yes Yes (2) Yes No (1} Quarterly Spent Fuel Pit PP-31N No Yes Yes Yes Yes Yes Quarterly Cooling (5136) PP-31S No Yes Yes Yes Yes Yes Quarterly Jacket Water QT-130-AB1 No Yes Yes Yes Yes Yes Quarterly (5151B) QT-130-AB2 No Yes Yes Yes Yes Yes Quarterly QT-130-CD1 No Yes Yes Yes Yes Yes Quarterly QT-130-CD2 No Yes Yes Yes Yes Yes Quarterly a These pumps are tested on test, bypass or minimum flow .loops - per Section XI Subarticle IWP-1400.
b Inlet pressure measurement is in head of liquid, ft.
c Bearing temperatures will be measured annually, per Section XI IWP-3300 except as noted.
(1) Refer to Code Relief Request I (2) Refer to Code Relief Request II Revision 2 Page 3 of 5 2/5/90
'E I'
DONALD C. COOK NUCLEAR PLANT - UNITS NO. 1 AND 2 PUMP INSERVICE TEST PROGRAM CODE RELIEF REQUEST I Bearing Temperature Measurement We believe that the intent of Paragraph IWP-4310 is to exempt those pump bearings in the main flow path from temperature measurement requirements.
However, if code relief is required, we request that the Diesel Fuel Oil Transfer Pumps be exempt from bearing temperature requirements as stated in Section XI, Subarticle IWP-3300.
The inboard and outboard sleeve bearings on those two HP gear pumps are lubricated and cooled by the pumped fluid. Temperature readings are therefore inconclusive since bearing measurement points are not responsive to the changes in bearing temperatures.
Bearing problems on gear pumps can be more readily identified by degradation of pump capacity. Flow rate deterioration indicates the existence of excessive clearance due to bearing 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.
Revision 2 Page 4 of 5 2/5/90
DONALD C. COOK NUCLEAR PLANT - UNITS NO. 1 AND 2 PUMP INSERVICE TEST PROGRAM CODE RELIEF REQUEST II Duration of Tests Request that the duration of pump operation for testing, per Section XI Subarticle IWP-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 stabilized.
Revision 2 Page 5 of 5 2/5/90
ATTACHMENT 2 TO AEP:NRC'0969R INSERVICE TESTING PROGRAM FOR VALVES, UNIT 1, REVISION 3, FEBRUARY 5, 1990
ATTACHMENT 3 TO AEP:NRC:0969R INSERVICE TESTING PROGRAM FOR VALVES, UNIT 2, REVISION 3, FEBRUARY 5, 1990
ATTACHMENT 4 TO AEP:NRC:0969R
SUMMARY
OF REVISION 2, IST PUMP PROGRAM AND REVISION 3, IST VALVE PROGRAM to AEP:NRC:0969R Page 1
SUMMARY
OF REVISIONS The IST Program (Second 10-Year Inspection Interval) for Donald C.
Cook Nuclear Plant, Units 1 and 2 has been revised (Pump Program Revision 2, Valve Program Revision 3) to reflect the changes required by the Safety Evaluation Report (SER) dated August. 29, 1989, Supplemental SER (SSER) dated November 28, 1989 and Generic Letter 89-04.
- 1) The specific issues described in Enclosure 3 of the SSER, and our responses to each, are listed below:
A endix C No. 17 3.2.1 Flow instrumentation will be installed on the spent fuel pit cooling pumps (tentative completion date is January 31, 1990).
Response: Installation of the flow instrumentation was completed by January 31, 1990. Therefore, Code Relief Request III has been deleted from the pump program.
A endix C No. 3 4.2.1.1 Closure of main steam to turbine driven auxiliary feedwater pump (TDAFP) check valves (MS-108-2 and -3) will be verified in accordance with Generic Letter 89-04.
Response: The IST Valve Program has been revised to reflect this change.
A endix C No. 14 4.-4.1.1 The essential service water to auxiliary feed pump suction valves will be tested on a cold shutdown frequency.
Response: The IST Valve Program has been revised to reflect this change.
A endix C No. 5 A revision to the IST program notes will indicate that the TDAFP suction and discharge valves will be part stroke exercised quarterly and full stroke exercised at a cold shutdown frequency. The staff concurred with the licensee's resolution.
Response: The IST Valve Program has been revised to reflect this change.
to AEP:NRC:0969R Page 2 A endix C No. 2 4.1.1 The IST program will be revised to designate valves with maximum limiting stroke times of up to two seconds as "fast acting, valves". The staff agreed that stroke times do not need to be specified in the program and concurred with the licensee's resolution.
Response: The IST Valve Program has been revised to reflect this change. All power operated valves that are stroke timed are indicated by ET-XXX in the Valve Summary Sheets. Stroke time limiting values have been removed from the IST program and are identified and controlled via the Plant Technical Data Book and plant procedures. This has been referenced in Figure 1 and Figure 3 of the IST Program. This change was made per the NRC recommendation made during the meeting.
A endix C No. 3 The program will be changed to indicate that disassembly of check valves will be performed in accordance with Generic Letter 89-04 (disassembly accepted instead of testing in some cases where testing proved impractical). The staff indicated some concern about the possibility of incorrect reassembly of bonnet-hinged check valves. AEP indicated that bonnet-hinged check valves can be backflow tested and would not have to be disassembled under the IST program.
AEP requested clarification on the requirement to test different sized valves of the same type and manufacturer at a given frequency. The staff suggested that AEP might want to consider separating the valve sizes into two groups and changing the frequency, as allowed by Generic Letter 89-04, if it can be justified based on in-service experience.
Response: The Containment Spray Check Valves (CTS-127E&W,-131 E&W and RH-141 and -142) are bonnet-hinged design valves.
These valves are seat leakage tested to verify backflow before (as found) and after disassembly which ensures proper reassembly of the valve internals.
The IST Program has been revised to reference GL 89-04 for alternative testing method requirements (i.e., grouping, frequency, etc.) for the check valves as required.
A endix C No. 12-AEP stated that the diesel generator air start valves XRV-221 and -222 have no required fail safe position and fail safe testing should not be required. (Valves fail in one position to AEP:NRC:0969R Page 3 on loss of instrument air and in the other position on loss of DC power.) The staff concurred with the licensee's conclusion.
Response: The IST valve Program has been revised to reflect this change for starting air valves. In addition, code relief notes for valves XRV-221, -222, -226 and -227 (Starting air) and -XRV-220 and -225 (Jet assist) for the emergency diesel generators also have been revised to reflect changes in testing frequency due to new Technical Specification 4.8.1.1.2 requirements approved by the NRC.
A endix C No. 16 AEP clarified that no relief was required for testing of essential service water to diesel generator cooling check valves since all required tests for Section XI are already performed.
Response: The IST Valve'Program (notes) has been revised to clarify above.
A endix C No. 4 4.3.1.1 AEP discussed the burden involved in disassembly of feedwater header check valves (FW-118-1, -2, -3 and -4) at every cold shutdown and proposed to disassemble the valves on a refueling outage frequency. The staff found the licensee's resolution acceptable.
Response: The IST Valve Program has been revised to reflect this change.
A endix C No. 9 4.7.1.1 Additional'ustification was also provided for not fail safe testing and stroke timing normal charging control valves QRV-200 and -251. AEP contends that stroke timing is impractical because there is no local or remote position indicator on the valves. The staff agreed that locally verifying smooth full travel of the valve would be adequate.
AEP explained to the staff that QRV-200 does not have a fail safe position. Furthermore, AEP indicated that fail safe testing of the QRV-251 valve was impractical and would require disassembly of the air supply line. However," AEP committed to investigate possible ways in which to perform fail safe testing of QRV-251 (e.g., adding a valve to the air supply line if nec'essary).
Response: The IST Valve Program has been revised to reflect this change. To "fail-safe" test valve QRV-251, an alternative testing method is being proposed which duplicates the fail-safe condition using the existing control =scheme. This method is described in the code relief notes for QRV-251 in lieu of modification (install hand valves in the control air lines).
to AEP:NRC:0969R Page 4 t
A endix C No. 13 4.8.1.1 The staff agreed with the AEP justification for fail safe testing the letdown heat exchanger temperature control valve (CRV-470) only on a cold shutdown frequency (i.e., not at power).
Response: The IST Program has been revised to reflect this change.
A endix C No. 8 4.6.1.3 AEP's proposal for testing containment isolation check valve (SI-189) was consistent with Generic Letter 89-04 but still a code deviation. The staff determined that the licensee's proposal to part stroke test on a cold shutdown frequency and full stroke test on a refueling outage frequency is acceptable.
Response: The IST Program has been revised to reflect this change. Full stroke testing in the open position will be done in accordance with the alternative method described in GL 89-04 as described in the code relief notes.
A endix C No. 11 With regard to RHR pump discharge line check valves (RHR-108E and -108W): AEP proposed to conduct a part stroke test on a quarterly basis and a full stroke test during cold shutdown.
The staff agreed with this since full stroke of the valve at full power is undesirable and since the line isn't instrumented for full flow.
Response: The IST Program has been revised to reflect this change.
A endix C No. 7 4.6.2 AEP proposed to test the reactor head vent valves and the pressurizer vent valves during cold shutdowns when the RCS pressure is less than or equal to 80 psig for personnel safety consider'ations. The staff asked the licensee to explain the basis for the 80 psig pressure constraint'. AEP notified the, NRC Project Manager on 11/15/89 that these valves would be tested during cold shutdown in accordance with Code requirements.
Response: The IST Program has been revised to reflect this change.
- 2) The entire IST Valve Program has been re-reviewed and revised as necessary for clarity and consistency to alleviate anomalies identified in the SER (i.e., SER Appendix C, Items 6, 10 and 15).
to AEP:NRC:0969R Page 5 SER A endix C Item 6 The NRC staff position regarding containment isolation valve testing is explained in Generic'Letter 89-04. Testing containment isolation valves in accordance with the requirements of 10 CFR 50, Appendix J, and Section XI, IWV-3426 and 3427(a), is acceptable. Since this position represents a deviation from the Code requirements, it should be documented in the IST Program.
Response: The IST Program has been revised to document testing containment isolation valves in accordance with the requirements of 10 CFR 50, Appendix J and Section XI, IWV-3426 and 3427(a).
SER A endix C Item 10 The licensee lists the testing being performed on valves SI-170 Ll, L2, L3 and L4 as note 6. Note 6 is the relief request from exercising valves SI-161 Ll, L2, L3 and L4. This discrepancy should be corrected.
Response: The IST Program has been revised to correct this discrepancy.
SER A endix C Item 15 The Cook Nuclear Plant IST Program valve, table lists valves IM0-330, -331, -340 and -350 as being tested quarterly in accordance with Section XI. The licensee requested relief from quarterly testing requirements in letters to the NRC dated October 31, 1986, and November 20, 1987, and the licensee was granted interim relief." Additionally, this relief request should be included in the IST Program.
Response: The IST Program has been revised to include relief request for valves IMO-340 and -350 as granted by the NRC dated January 30, 1989.
- 3) In addition, the following changes have been made to the program.
Code relief requests or cold shutdown justifications for the following valves have been revised to clarify the testing
.methods and/or frequency that will be employed at the Cook Nuclear Plant.
WRV-721, -723, -725 and 727-Unit-1 (Code Relief ¹3)
WRV-722, -724, -726 and 728-Unit-2 Drawing No. 1-5113 Drawing No. 2-5113 XRV-220-Jet Assist (Turbo Charger)-Unit-1 (Code Relief ¹3 and 4)
~I N
to AEP:NRC:0969R Page 6 XRV-225-Jet Assist (Turbo "Charger)-Unit-2'rawing No.
1-5151B and D XRV-221 and -222-Starting Air-Unit 1 Drawing No.
2-5151B and D XRV-226 and -227-Starting Air-Unit 1 CTS-109 & -110 -Units 1 and 2 (Cold Shutdown Justification ¹6)
Drawing No. 1-5144 Drawing No. 2-5144 VRV-315 and -325 -Units 1 and 2 ,(Code Relief ¹1)
Drawing No. 1-5149 Drawing No. 2-5149 Revised permissible leakage values per calculation ECP-1-2-I0-01 Rev. l.
1-CTS-131 East & West Paragraph ¹2, 2-CTS-131 East & West Attachment A The following check valves have been removed from the program since the valve internals were removed under Modification Package 12-MM-019.
DG-131A and -C-Unit-1 Drawing No. 1-5151B and D DG-133A and -C-Unit-1 Drawing No. 2-5151B and D DG-132A and -C-Unit-2 DG-134A and -C-Unit-2 All notes in the IST Program have been revised to state whether it is a code relief or cold shutdown justification or comment associated with specific valve(s) as suggested by the NRC during the meeting (Appendix C, No. 1).
The diesel jacket water cooling pumps have been incorporated into the program (Drawing No. 1-5151B and 2-5151B) due to review of Generic Letter 89-04. The pumps will be entered into the program by July 1, 1990, the" additional time allowing for procedures to be written.