ML20217C431
| ML20217C431 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 04/17/1998 |
| From: | Dawn Powell Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N98162, NUDOCS 9804230312 | |
| Download: ML20217C431 (2) | |
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Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR 171999 LR-N98162 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 ISOLATION ACTUATION INSTRUMENTATION TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 i
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Gentlemen:
On November 28, 1997, during Hope Creek's seventh refueling outage (RFO7), Engineering personnel determined that a flow orifice element (1BGFE-N040-G33) in the Reactor Water Cleanup (RWCU) was installed backwards.
This flow orifice element is used to generate the RWCU high delta flow containment isolation signal listed in Technical Specification Table 3.3.2-1.
As a result of this incorrect installation, PSE&G has implemented conservative administrative controls to ensure that the maximum allowable RWCU flow rates listed in Technical Specification Table 3.3.2-2 are not exceeded.
The incorrect installation of the RWCU flow orifice element was the subject of an NRC violation (VIO 10-03) issued in an inspection report dated February 3, 1998.
The purpose of this letter is to inform the NRC of PSE&G's continuing evaluation of this configuration and planned l
corrective actions.
Specifically, Engineering has continued to l
support the administrative controls implementing a four gallon per minute (gpm) reduction in the trip setpoint and allowed value listed in Technical Specification Table 3.3.2-2 for the RWCU high delta flow signal (i.e.,
differential flow trip setpoint of s 52 gpm and an allowable value of s 57.3 gpm vs. respective Technical Specification values of s 56.3 gpm and 5 61.3 gpm).
If further analysis of the existing RWCU flow orifice element installation indicates that a permanent reduction in the setpoint and allowable value is required, then PSE&G will prepare a License Change Request to revise the associated Technical Specification i
values.
If a License Change Request is required, then PSE&G will submit the application in time to support Technical Specification Amendment approval prior to completing the next refueling outage (RF08).
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APR 171998 Document Control Desk j LR-N98162 a
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Should you have any questions or comments on this transmittal, do not hesitate to contact us.
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Sincerely, ct4t[
David R.
Powell Director -
Licensing / Regulation & Fuels C
Mr.
H.
Miller, Administrator - Region I U.
S.
Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr.
R.
Ennis, Licensing Project Manager - HC (Acting)
U.
S.
Nuclear Regulatory Commission One White Flint North j
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 j
Trenton, NJ 08625
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