ML20216C832
| ML20216C832 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/07/1998 |
| From: | Eric Simpson Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N98172, NUDOCS 9804150061 | |
| Download: ML20216C832 (4) | |
Text
.o RMe hmce Ekrtrc and Gas Company E. C. Simpson Public Service Electric and Gas Company P O. Box 236, Hancocks Bridge. NJ 08038 600-339-1700 Svet V<e nMent Ni Enyneenng APR 0719M LR-N981T2' United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 ASME BOILER AND PRESSURE VESSEL CODE PUMP INSERVICE TESTING RELIEF REQUEST HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 Gentlemen:
Public Service Electric and Gas Company (PSE&G) hereby requests relief from the requirements to declare a pump inoperable if the baseline vibration levels exceed the " required action" levels as prescribed in ASME/ ANSI OM-1987, Addenda 1988, Part 6, Section 6.
In lieu of declaring the pump inoperable, Hope Creek proposes to provide the ability to analyze the test data and determine if the pump is still capable of performing its intended safety function consistent with the requirements contained in OMc-1994 Addenda (ISTB 6.2.2) and the OM 1995 Edition (ISTB 5.2.2).
Since the request affects the current implementation of the Hope Creek Inservice Testing Program, prompt resolution of this relief request is required.
An essentially identical relief request, submitted by Southern Company for Plant Hatch, was reviewed and approved by the NRC in an SER dated, April 12, 1996.
Should you have any questions or comments on this transmittal, do not hesitate to contact us.
Sincerel 1
Attachment I
(DO 1
9804150061 980407 PDR ADOCK 05000354 P
@ Pnntud on Rocycted Paper
6 APR 071990 Documsnt Control Desk LR-N98172 C
Mr. H. Miller, Administrator - Region I U.
S.
Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P.. Ennis, Licensing Project Manager - HC U.
S.
Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr.
D. Jaffe, Licensing Project Manager - HC (Acting)
U.
S.
Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852
)
Mr.
S. Pindale (X24)
USNRC Senior Resident Inspector - HC Mr.
K.
Tosch, Manager IV Bureau of Nuclear Engineering P.
O.
Box 415 Trenton, NJ 08625 l
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PUMP RELIEF REQUEST P - 03 SYSTEM:
Allincluded in IST Program PUMPS:
Allincluded in IST Program CLASS:
2 and 3 TEST REQUIREMENT:
OMa-1988, Part 6, Section 6, Paragraph 6.1 states, in part - If
- deviations fall within the required action range of Table 3, the pun p shall be declared inoperable until the cause of the deviation has been determined and the condition corrected.
BASIS FOR RELIEF:
The 1983 ASME Section XI Code, subsection IWP-3230(c) stated that; "Correctise action shall be either replacement or repair per IWP-3111, or shall be an analysis to demonstrate that the condition does not impair pump operability and that the pump will fulfill its function. A new set of j
reference values shall be established after such I
analysis."
i The OMc-1994 Addenda (ISTB 6.2.2) and the OM 1995 Edition (ISTB 6.2.2) both state that; "If the measured test parameter values fall within the required action range of Table 5.2.1-1, Table 5.2.1-2, Table 5.2.2-1, or Table 5.2.3-1, as applicable, the pump i
shall be declared inoperable until either the cause of the j
deviation has been determined and the condition is corrected, or an analysis of the pump is performed and new reference values are established in accordance with ISTB 4.6."
The Code applicable for the first interval IST Program and the latest issued Code both provide for analysis of pump test data in lieu of repair or replacement of the pump if the test parameters fall within the required action range. The OMa Code-1988 Edition did not include such provisions. Communications with members of the OM Code Committee indicate that this was an oversight and that it was never intended to delete the ability to analyze the test data and determine if the pump is still capable of performing its intended safety function.
ALTERNATE TESTING:
Should pump test parameters fall within the required action range I
ofTable 3 (OMa Code 1988 Edition), then the OM Code 1995 Edition, subsection ISTB 6.2.2 will be utilized. Since subsection ISTB 4.6 in the 1995 Code Edition references ISTB 6.2.2, subsection ISTB 4.6 from the OM Code 1995 Edition will also be applied.
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