ML17306A994
| ML17306A994 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 09/22/1992 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Conway W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| References | |
| TAC-M84132, TAC-M84133, TAC-M84134, NUDOCS 9209280320 | |
| Download: ML17306A994 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 September 22, 1992 Docket Nos.
50-528, 50-529 and 50-530 Hr. William F.
Conway Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999
- Phoenix, Arizona 85072-3999
Dear Hr. Conway:
SUBJECT:
COMPLETION OF REVIEW OF WYLE TEST REPORT ON SEISMIC TESTING OF EXIDE BATTERIES PALO VERDE NUCLEAR GENERATING STATION (TAC NOS. H84132,
- M84133, AND N84134)
We have completed our review of the "Seismic Simulation Test Program on Six Naturally-Aged Type 2GN Exide Batteries Wyle Test Report No. 42679-1."
The test report contains the results of simulated seismic tests of six naturally-aged and cracked Exide Type 2GN Batteries subject to the Required
Response
Spectra (RRS) at the battery location in the Palo Verde Nuclear Generating Station.
Although the staff did not conduct a detailed review of the input motion, it appears that the test procedures and the test input adequately follow the IEEE Standard 344-1975, except that the functional operability (voltage, current, etc.) of the batteries was not monitored.
The test report concluded that the specimens still possessed some structural integrity to withstand the RRS without causing a catastrophic failure.
However, the staff finds the results of the Wyle tests do not provide adequate basis to demonstrate that the aged and cracked batteries provide sufficient capacity and capability to perform their safety function in the event of an earthquake.
The staff's rationale for this conclusion is provided in the following discussion.
Large lead storage batteries are used in nuclear power plants as a source of emergency power for vital instrumentation and control systems such as electrical distribution breaker control for engineering safety features, inverters for reactor protection instrument channels, and certain other safety-related equipment.
Since safety-related lead storage batteries must meet design specifications throughout the batteries'nstalled life, the aged and cracked batteries must be qualified to the plant design specifications.
In qualifying the aged and cracked battery cells, the batteries must undergo capacity tests to show that the aged and cracked battery cells are capable of performing their safety function before, during, and after a seismic event as delineated in Section 8.3. 1. 1 of ANSI/IEEE Standard 535.
- However, these capacity tests were not performed in the subject test program.
A further deficiency was noted in the Wyle test report concerning the lack of acceptance criteria and/or requirements for:
(1) monitoring of the electrical functions (such as voltage, current, discharge rate for battery capacity,
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Hr. William F.
Conway etc.) before, during, and after the tests.
Section 6.3.1 of the Wyle test report concluded that "the Batteries were still functioning electrically;"
- however, the report did not discuss how this determination was made; (2) initiating new cracks and/or propagating existing cracks in the battery cell cover and casing;
- and, (3) monitoring the acceptable fluid level in the battery cells during and after the test.
The Wyle test results indicated that some of the existing cracks in the battery covers propagated and some new cracks appeared.
It has also indicated that some battery fluid was lost, but it was unclear whether this loss has affected the electrical function.
Based on the above, the staff concludes that the Wyle test has neither demonstrated the seismic qualification of aged and cracked batteries, nor provided an adequate justification for their continued service.
Therefore, batteries with cracks, whether in the cover or in the jar, should be replaced promptly.
Sincerely, cc:
See next page Charles H. Trammell, Senior Project Hanager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regualtion
Mr. William F.
Conway Arizona Public Service Company Palo Verde CC:
Nancy C. Loftin, Esq.
Corporate Secretary
& Counsel Arizona Public Service Company P.
O.
Box 53999, Mail Station 9068
- Phoenix, Arizona 85072-3999 James A. Beoletto, Esq.
Southern California Edison Company P. 0.
Box 800
- Rosemead, California 91770 Senior Resident Inspector U.S. Nuclear Regulatory Commission HC-03 Box 293-NR
- Buckeye, Arizona 85326 Regional Administrator, Region V
U.
S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. William A. Wright, Acting Director Arizona Radiation Regulatory Agency 4814 South 40 Street
- Phoenix, Arizona 85040 Chairman Maricopa County Board of Supervisors 111 South Third Avenue
- Phoenix, Arizona 85003 Jack R.
- Newman, Esq.
Newman
& Holtzinger, P.C.
1615 L Street, N.W., Suite 1000 Washington, D.C.
20036 Curtis Hoskins Executive Vice President and Chief Operating Officer Palo Verde Services 2025 N. 3rd Street, Suite 220
- Phoenix, Arizona 85004 Roy P.
Lessey, Jr.,
Esq.
Bradley W. Jones, Esq.
Arkin, Gump, Strauss, Hauer and Feld El Paso Electric Company 1333 New Hampshire Ave., Suite 400 Washington, D.C.
20036
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Hr. William F.
Conway September 22, 1992 etc.) before, during, and after the tests.
Section 6.3.1 of the Wyle test report concluded that "the Batteries were still functioning electrically;"
- however, the report did not discuss how this determination was made; (2)
, initiating new cracks and/or propagating existing cracks in the battery, cell',
cover and casing;
- and, (3) monitoring the acceptable fluid level in the battery cells during and after the test.
The Wyle test results indicated that some of the existing cracks in the battery covers propagated and some new cracks appeared.
It has also indicated that some battery fluid was lost, but it was unclear whether this loss has affected the electrical function.
Based on the above, the staff concludes that the Wyle test has neither demonstrated the seismic qualification of aged and cracked batteries, nor provided an adequate justification for their continued service.
Therefore, batteries with cracks, whether in the cover or in the jar, should be replaced promptly.
Sincerely, cc:
See next page original signed by Charles H. Trammell, Senior Project Manager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regualtion DISTRIBUTION:
Docket File BBoger CTrammell ACRS(10)
P315 N. Fid NRC 8 Local PDRs HVirgilio DFoster PDV Plant File I(J Ce~~<.
PDV Reading File TQuay
- OGC, 15B18
- KPerkins, RV OFC NAME DATE PDV LA DFoster 09 h 92 PD CT ammell:lh 09 lp 92 PDV/D TQuay 09 (4 92 OFFICIAL RECORD COPY DOCUMENT NAME:PV84132.LTR
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September 22, 1
Docket Nos.
50-528, 50-529 and 50-530 Hr. William F.
Conway Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999
- Phoenix, Arizona 85072-3999
Dear Hr. Conway:
SUBJECT:
COMPLETION OF REVIEW OF WYLE TEST REPORT ON SEISMIC TESTING OF EXIDE BATTERIES PALO VERDE NUCLEAR GENERATING STATION (TAC NOS. H84132,
- H84133, AND H84134)
DISTRIBUTION:
+Docket F lej NRC
& Local PDRs PDV Reading File PDV Plant File BBoger HVirgilio TQuay CTrammell HFiel ds DFoster
P315
- KPerkins, RV