ML20117G123
| ML20117G123 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/15/1996 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M91368, TAC-M91369, NUDOCS 9605200449 | |
| Download: ML20117G123 (15) | |
Text
-
'buke Ibwer Company T C hicAfEERN AlcGuire Nuclear Generation Department Vice President 12700HagersFenyRoad(AIGolW)
(i&I)87548(C Hunterseslie, NC280784985 (701)8754809 Fax
(?)
r l3UKEPOWER
%J May 15, 1996 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.
20555
Subject:
McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Inservice Testing Program, Relief Request 1.4.2
Dear Sir:
By letter dated May 22, 1995, Duke Power Company was informed that certain relief requests dealing with the Inservice Testing Program for Pumps and Valves were approved provisionally and that Relief Request 1.4.2 had been approved for an interim period of one year from the date of the Safety Evaluation Report (SER).
The SER confirmed that Duke Power agreed that an interim period of one year would provide adequate time for further review of the potential options or to revise the request and include additional details on the impracticality or hardship of meeting the requirements of OM-6.
To this end, the Duke Power Company response to the concerns of the May 22, 1995 SER are herein presented for the review and approval of the Staff.
Should there be any questions regarding this matter, please contact John M. Washam at (704) 875-4181.
Very truly yours,
(.Sud 1
i 7/
McMeekin T.
200108 9605200449 960515' PDR ADOCK 0S000369 P
U.S. Nuclear Regulatory Commission May 15, 1996 Page 2 1
xc:
Mr.
S.D.
Ebneter Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St.,
NW, Suite 2900 Atlanta, Ga. 30323 Mr. Victor Nerses U.S. Nuclear Regulatory Commission Office of Nuclear Reactor, Regulation l
Washington, DC 20555 l
l Mr. George Maxwell Senior NRC Resident Inspector, McGuire 1
McGuire Nuclear Station l
l l
i i
9
(
2 l
9 f.
Response to the May 22, 1995 Safety Evaluation and Review of Responses to NRC Safety Evaluation Action Items and Revised Relief Request for the McGuire Nuclear Station, Units 1 and 2, Inservice Testing Program (TAC NOS. M91368 and M91369)
The proposed course of action for the Diesel Generator Engine Fuel Oil System (FD) pumps is to:
(1) Place the FD pumps in the Supplemental Test Program.
At a 6 month frequency, the FD pump performance will be monitored to ensure that flow does not decrease to less than 200 % of flow required (approximately 12.5 gpm).
Current pump flow rates are at approximately 22 gpm, (2) Remove the FD pumps from the IST Program and delete Relief Request 1.4.2.
NUREG-1482, 3.4 states the following:
Pending endorsement of OM codes and standards which specifically address skid-mounted components which are subject to j
IST, the staff has determined that the testing of the major component is an acceptable means for verifying the operational readiness of the skid-mounted
)
and component subassemblies if the licensee documents this approach in the IST Program.
This is acceptable for both Code class components and non-Code class componunts tested and tracked by the IST Program.
The proposed revision of ISTB (Inservice Testing of Pumps in Light-Water Reactor Power Plants) includes exclusion of " Skid-mounted pumps and component subassemblies that are tested as part of the major component and are determined by the Owner to be adequately tested" (ISTB 1.2).
A similar change is in the proposed revision of ISTC, for valves.
These changes have been approved but not yet issued.
A
" White Paper" on the Proposed Change to ISTB 1.2 Exclusions, Pumps That Are Part of Skid-Mounted Components, states that the proposed change is applicable provided: (1) the pumps are part of the l
(skid-mounted) major component, (2) the pumps receive i
testing under the major component test programs, and l
(3) the owner has determined that the major component l
test adequately assesses the operational readiness of the individual skid-mounted component.
The White Paper also states that "It is the intent of the authors of the proposed change to allow the exemption of skid-1
. ~
l 1 4.,.
mounted components, even though those components are not directly located on the skid, provided the component is dedicated to the major component and is adequately tested during the major component test."
OM-16 (Inservice Testing and Maintenance of Diesel Drives in Nuclear Power Plants) includes the fuel oil system within its scope; the FD system must function to support the diesel.
The operational readiness of the FD transfer pumps is demonstrated by the monthly 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> diesel runs, in which the transfer pump will typically cycle 5 times.
FD pump operation is also required for the 18 month diesel runs (these are 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> runs)
As a measure to ensure FD pump performance in addition to its demonstrated readiness for the diesel runs (failure of the pump to run would result in diesel. shutdown during the runs), every 6 months the flow rate of the FD pumps will be measured.
The authorized method of measuring day tank level over time will be used (as is currently used).
The OM-6 requirement of 2 minutes testing will not apply to this test, which is outside of this scope.
(3) Send an inquiry to the Code Committee for ISTB with the above information attached.
It appears that the proposed test method meets the intent of the White Paper (FD pumps are part of the major component, receive testing under the diesel test programs, and the Supplemental Program will ensure not only operational readiness, but any significant FD pump degradation is detected).
These measures will not require any reclassification of the FD pumps from ASME Class 3.
FD pump data over the past two years indicates the following:
FD Pump 1A:
Run Time Discharge Pressure Average Flow Range (PSIG)
(GPM) 15 sec 7.5-9 75 sec 12-20 90 sec 13-21 21 FD Pump 1A:
Run Time Discharge Pressure Average Flow Range (PSIG)
(GPM) 15 sec 7-10.5 i
75 see 12.3-15 90 sec 14-17 21.87 4
i 2
t
~
FD Pump 2A:
Run Time Discharge Pressure Average Flow Range (PSIG)
(GPM) 15 sec 20-23.5 75 sec 22-24.25 90 sec Not Achievable 21.8 FD Pump 2B:
Run Time Discharge Pressure Average Flow Range (PSIG)
(GPM) 15 sec 20.6-24 75 sec 22-25 90 sec 24 (Obtained once) 22.29 3
The above data shows acceptable FD pump operation over a wide range of discharge pressure (which is dependent on day tank level and the setpoint of the backpressure control valve).
Flow rate shows a margin of approximately 9 gpm over the 200 % point at which corrective action will be taken on degrading FD pump performance under the IST Supplemental Program.
Test Acceptance Criteria (TAC) Sheet MCTC-1609-FD.P001-01, Rev. 0 will need to be revised to delete the reference to ASME Section XI Subsection IWP.
As stated on this TAC sheet, the design basis of the Diesel Fuel Oil Transfer Pumps is to transfer fuel oil from the respective Diesel Fuel Oil Storage Tank to the respective Fuel Oil Day Tank.
The FD Pump must be capable of transferring fuel oil from the other train's Diesel Fuel Oil Storage Tank to its respective Fuel Oil Day Tank.
The FD Pump must provide a minimum fuel oil flow to meet the fuel consumption requirements of the least efficient diesel generator.
In addition to this, the proper operation of the backpressure relief valve
(> 10 psig) ensures that the Fuel Oil Storage Tank will not gravity feed to the day tank.
These parameters will continue to be tested, outside of the IST program.
Technical Specification testing will continue as before, per Tech Spec Surveillance Requirements 4.8.1.1.2 and 4.8.1.2 (transfer pump starts and transfers fuel from the storage system to the day tank, on the normal DG test j
schedule), and 4.8.1.1.2.e.12 (transfer pump transfers fuel
]
oil from each fuel storage tank to the day tank of each diesel via the installed cross-connection lines, once per 18 months).
In conclusion, it is felt that the above approach will ensure the operational readiness of the Diesel Fuel Oil Transfer Pumps, and detect any degradation at a point sufficiently above the required flow rate.
Past performance of these pumps indicates operation at a point far exceeding l
3
the flow required.
A review of NUREG-1482 and Code changes indicates that these pumps are not within the scope of OM-6.
The submittal revisions should be considered as Revision 23 and 18 of the McGuire inservice Testing Program, Units 1 and 2 respectively.
The only changes to the submittal are as follows:
1)
Section I.2 (Unit 1), delete 1FDPU0054 and 1FDPU0055 from the Unit 1 Pump Inservice Testing General Data and Specific Data listings.
2)
Section I.4 (Unit 1), delete Specific Relief Request-1.4.2 (2 pages, leave as blanks with " Specific Relief Request 1.4.,2 Deleted per Rev. 23").
3)
Section I.2 (Unit 2) delete 2FDPU0054 and 2FDFU005E from the Unit 2 Pump Inservice General Data and Specific Data listings.
4)
Section I.4 (Unit 2), delete Speutfic Rolief Request 1.4.2 (2 pages, leave as blanks with "S w ific Relief 3
Request 1.4.2 Deleted per Rev. 18").
The eight revised pages are attached as Attachment 1.
Please remove the corresponding pages in the current submittal and replace them with attachment 1.
No other changes are being made per Revisions 23 (Unit 1) and 18 (Unit 2).
The
(
remaining relief requests addressed in the May 22, 1995, SER and the April 12, 1995, teleconference do not require changes.
t o
4
Response to May 22,1995 SER Replace the corresponding 8 Pages of the current Pump and Valve Inservice Testing Program with the attached pages:
Section I.2 (Unit 1) pp. I and 2 of 12 Section I.4 (Unit 1) pp. 2 and 3 of 1I
)
Section I.2 (Unit 2) pp. I and 2 of 8 1
Section I.4 (Unit 2) pp. 2 and 3 of 11
\\
f
UNIT 1 - McGUIRE NUCLEAR STATION
~
Pump Inservice Testing General Dato Code Pump ID. Nuram Description Class Flow Degram Applicable Relief Requests Test Frequency Remarks ICAPU0001 Motor Criven Auxiliary 3
MC-1592-1.1 RR-l.3.1. RR-l.4.1 Quarterly NONE Feedwater Pump 1 A 1CAPU0002 Motor Driven Auxiliary 3
MC-1592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump 1B ICAPU0003 Turbine Driven Auxiliary 3
MC-1592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump #1 1KCPU0001 Component Cooling 3
MC-1573-1.0 RR-l.3.1, RR-l.4.3 Quarterly NONE Water Pump 1 A1 1KCPU0002 Component Cooling 3
MC-1573-1.0 RR-l.3.1, RR-l.4.3 Quarterly NONE Water Pump 1 A2 1KCPU0003 Component Cooling 3
MC-1573-10 RR-l.3.1, RR-l.4.3 Quarterly NONE Water Pump 1B1 SECTloN L2 4/30/96 1 OF 12
~
UNIT 1 - McGUlRE NUCLEAR STATION Pump inservice Testing Specific Data Dischorge Differenflol Reference Pump ID. Number speed inlet Pressure Pressure Pressure Vibrofion Flow Rote Pump Type Revision 1CAPU0001 Not Required RR-l.4.1 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 1CAPU0002 Not Required RR-l.4.1 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements ICAPU0003 Meets Code RR-l.4.1 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements Requirements 1KCPU0001 Not Required RR-l.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements IKCPU0002 Not Required RR-IA.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 1KCPU0003 Not Required RR-l.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements SECTION l.2 4/30/96 2 oF 12
McGuire Unit 1 i
i Specific Relief Reauest (Specific Relief Request 1.4.2 Deleted per Rev. 23) i 1
1 04/30/96 SECTION l.4 2 OF 11
McGuire Unit 2 Specific Relief Reauest I
l i
i 1
l l
\\
(Specific Relief Request 1.4.2 Deleted per Rev.18) 1 l
l l
l l
I l
r i
4 04,'30/96 CECTION l.4 2 OF 11
McGuire Unit 1 Specific Relief Rp_ quest l
1 j
a l
(Specific Relief Request 1.4.2 Deleted per Rev. 23) s M
l t
1 l
t 4
Y l
l i
i l
l 04/30/96 SECTION 1.4 3 OF 11 1
4 McGuire Unit 2 Spesific Relief Reque11 I
l 1
l l
(Specific Relief Request 1.4.2 Deleted per Rev.18)
OMW SECTION 1.4 3 OF 11
UNIT 2 - McGUIRE NUCLEAR STATION Pump Inservice Testing General Data Code Pump ID. Number Description Class Flow Diagram Applicable Relief Requests Test Frequency Remarks 2CAPU0001 Motor Driven Auxiliary 3
MC-2592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump 2A 2CAPU0002 Motor Driven Auxiliary 3
MC-2592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump 2B 2CAPU0003 Turbine Driven Auxiliary 3
MC-2592-1.1 RR-l.3.1, RR-l.4.1 Quarterly NONE Feedwater Pump #2 2KCPU0001 Component Cooling 3
MC-2573-1.0 RR-1.3.1, RR-l.4.3 Quarterly NONE Water Pump 2A1 2KCPU0002 Componer,t Cooling 3
MC-2573-1.0 RR-l.3.1, RR-l.4.3 Quarterly NONE Water Pump 2A2 2KCPU0003 Component Cooling 3
MC-2573-1.0 RR-l.3.1, RR-l.4.3 Quarterly NONE Water Pump 2B1 SECTioN 1.2 4/30/96 1oF8
UNIT 2 - McGUIRE NUCLEAR STATION Pump inservice Testing Specific Dato Discharge Differential Reference Pump ID. Number Speed inlet Pressure Pressure Pressure Vibration Flow Role Pump Type Revision 2CAPU0001 Not Required RR-l.4.1 Meets Code Meets Code RR-l.3.1 Meet: Code Centrifugal Requirernents Requirements Requirements 2CAPU0002 Not Required RR-l.4.1 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 2CAPU0003 Meets Code RR-l.4.1 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements Requirements 2KCPU0001 Not Rec;uired RR-l.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 2KCPU0002 Not Required RR-l.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements 1
2KCPU0003 Not Required RR-l.4.3 Meets Code Meets Code RR-l.3.1 Meets Code Centrifugal Requirements Requirements Requirements SECTioN l.2 4/30/96 2oF8
- -