ML20247F353
| ML20247F353 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/08/1989 |
| From: | Loflin L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-89-254, NUDOCS 8909180145 | |
| Download: ML20247F353 (4) | |
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' SERIAL: NLS-89-254:
-10CFR50.55a SEP 0 81989
!b, United States Nuclear:Regul'atory Commission ATTENTION: Document. Control. Desk
' Washington, DC-20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1'AND 2-DOCKET.NOS.. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62
- IN-SERVICE TESTING PROGRAM RELIEF REQUEST PR-01 AND VR-12
"(NRC TAC NOS. 63523 AND 63524)-
Gentlemen:
L0n August 17, 1989, Carolina Power & Light Company (CP&L) held a conference-ccall with NRC.and their contractor to discuss the Relief Requests PR-01 and VR-12' contained in our November 24, 1987 In-Service Testing Program submittal.-. During that call',. CP&L agreed to provide more detail for the basis of these, relief requests.
- Enclosed are t'he revised relief requests PR-01 and VR-12.
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'Should you have any questions, please contact Mr. D. B. Bates at
-(919) 546-6154.
Yours very truly, f
C L. I. Lo in Manag Nuclear Licens ng Section DBB/crs: -(472CRS)
Enclosures cc:.
Mr. S. D. Ebneter Mr. W. H.:Ruland
-Mr. E. G. Tourigny 8909180145 890908
/
ADOCK05000gg4 PDR P
('t 411 Fayetteville Street e P. O. Box 1551
- Raleigh. N. C. 27602 womtaes
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- p RELIEF REQUEST NO. PR-01 l
. COMPONENT: Nuclear. Service Water. Pumps:
1-SW-N-P-1A, 1B' 2-SW-N-P-2A, 2B Conventional Service Water Pumps:
1-SW-C-P-1 A, 1B, '1 C 2-S4-C-P-2A, 2B, 2C
' Core Spray Pumps:
1-CS-P-1A, 1B and 2-CS-P-2A, 2B Residual Heat Removal Service' Water Pumps:
1-RHR-SW-P-1A, 1B, 1C, 1D 2-RHR-SW-P-2A, 2B, 2C, 2D Standby Liquid Control Pumps:
1-SLC-P-1 A, 1B 2-SLC-P-2A, 2B High Pressure Coolant' Injection Main and Booster Pumps:
1-HP CI-P-MN-1, 1-HP CI-P-BST-1 2-HPCI-P-MN-2, 2-HPCI-P-BST-2 Service Water Lubrication Water Pumps:
1-SW-LW-P-1A, 1B 2-SW-LW-P-2A, 2B Diesel Fuel Oil Transfer Pumps:
2-DG-0IL-P-1A, 1B, 2A, 2B, 3A, 3B, 4A, 4B
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Residual Heat Removal Pumps:
1-RHR-P-1A, 1B, 1C, 1D 2-RHR-P-2A, 2B, 2C, 2D Reactor Core Isolation Cooling Pumps:
1-RCIC-P-1 2-RCIC-P-2 FUNCTION:
Emergency core cooling Safety-related equipment cooling Safe reactor shutdown
' Diesel generator fuel oil supply CLASS:
2, 3 and NC TEST REQUIREMENT: Measure pump bearing temperature yearly.
BASIS FOR REl.IEF:
The referenced edition of the Code requires bearing temperatures to be recorded annually.
It has been demonstrated by experience that bearing temperature rise occurs only minutes prior to bearing failure.
Therefore, the detection of possible bearing failure by a yearly temperature measurement is extremely unlikely. A bearing will be seriously degraded prior to the detection of increased heat at the bearing housing. Quarterly vibration readings will achieve a much higher probability of detecting developing problems than annual bearing temperature readings. The small
-probability of detecting bearing failure by temperature measurement does not justify the additional pump operating time required to obtain the (472CRS)
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V measurements. Finally, IWP-3500 requires "three successive readings taken at ten-minute intervals that do not vary more than 3%."
Meeting this requirement L
for pumps having no recirculation test loop would be very difficult because the system water temperature, and consequently the lubricant temperature, are expected to drift more than 3% during 20 minutes. Also, the temperature of-the lubricating fluid will vary with ambient conditions and make meaningful data trending impractical.
As described above, a program of bearing temperature trends and the evaluation of the results would, in some cases, be difficult to analyze. Improper interpretation of results could result in unnecessary pump maintenance. In addition, it is impractical to measure bearing temperatures on many of the pumps in the program. Some specific examples are as follows:
-(1)
Core Spray: The pump bearings are water lubricated with suppression pool water.
(2)
Residual Heat Removal (RHR): The pump bearings are water lubricated with suppression pool water.
(3)
High Pressure Coolant Injection: The pump is driven by a steam turbine which exhausts steam into the pressure suppression chamber.
Extended run times to stabilize bearing temperatures could heat the suppression pool water to a temperature exceeding the Technical Specification limit.
ALTERNATE TESTING: Perform vibration testing on the pumps in accordance with 0M-6, " Inservice Testing of Pumps in Light-Water Reactor Power Plants."
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' RELIEF REQUEST NO. VR-12
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SYSTEM: Residual Heat Removal Core Spray COMPONENT: E11-F050A E11-F050B E21-F006A E21-F006B FUNCTION: Residual heat removal and core spray injection isolation valves.
CATEGORY: A/C CLASS:
1 TEST REQUIREMENT: Exercise check valves in the closed direction quarterly.
BASIS FOR RELIEF:
1.
Test at power:
The-RHR and core spray systems are low pressure systems.
The two automatic valves upstream of the check valves (E11-F015A,B and E11-F017A,B in RHR; E21-F004A,B and E21-F005A/B in Core Spray) are interlocked during power operation to maintain one valve closed for overpressurization protection.- This precludes opening the check valves at power to verify closure.
2.
Testing at cold shutdowns:
a.
Core Spray - Testing at cold shutdown would require injection of cold water into the vessel causing undesirable thermal cycling of the noLzles (ref. VR-09).
b.
RHR - The valves have no position indication, thus closure verification must be by a leakage test.
Such a test would require opening a 3/4" test connection upstream of the check valve.
Using only the static water head of the reactor vessel to close the valve would likely result in the leakage past the check valves (24" RHR, 10" Core Spray) exceeding the capacity of the test connection.
Performing a leakage test at function pressure differential would entail numerous plant evolutions including multiple loop swaps, significant draining, test pumps, and fill and venting which would significantly impact a nonrefueling outage.
ALTERNATE TESTING:
Exercise valves and confirm valve closure during pressure isolation valve leak testing at refueling.
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