ML20128J001
| ML20128J001 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/11/1993 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-93-2056, NUDOCS 9302170280 | |
| Download: ML20128J001 (2) | |
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GPU Nuclear Corporation a
Post Office Box 388 QQgf Route 9 South Forked River. New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number; February 11, 1993 C321-93-2056 U. S. Nuclear Regulatory Commission Att: Document Control Desk Washington, DC 20555
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Request for Relief from ASME Section XI, IWA-5250(a)(2)
Dear Sir:
Reference:
Letter No. C321-93-2041, Barton to USNRC dated February 4,1993.
On February 4,1993, GPU. Nuclear requested relief from the provisions of ASME Section XI, IWA-5250(a)(2). Subsequent to that letter, a teleconference was held between GPU Nuclear and several sections of the USNRC. This letter is being written to provide additional information to the USNRC as requested during that teleconference call.
The requested information is provided in Attachment I to this letter. If any additional information or nssistance is required, please contact Mr. John Rogers at 609.971.4893, p
g 6-J hn J. B:
in-V ce Presi nt and Director yster Creek JJB/JJR cc:
Administrator, Region I Senior Resident Inspector _
7 Oyster Creek NRC Project Manager j$ft3ggg{gj@$
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1.
l GPU Nuctear Corporation is a subsidiary ol General Pubbd Uhhhes Corporahon
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ATTACIIMENT I 1.
The relief requested in the referenced letter is specific to the leaking bolted connections which were discovered at the Oyster Creek Nuclear Generating -
Station during the NSSS Leak test which was conducted near the conclusion of the 14R refueling outage.
'2.
As described in request A in the referenced letter, the specific components for which reliefis requested are:
Recirculation Pump A, Body to Casing Seal-Recirculation Pump B, Body to Casing Seal Recirculation Pump C, Body to Casing Seal Recirculation Valve V-37-11 Main Steam Isolation Valve V-1-7 Main Steam Isolation Valve V-1-8 The specific components listed above we<e first inspected during the first days of the outage, while the plant was at normal temperature and pressure.
No leaks were identified at that time. An additional inspection for leakage will be conducted during the 1000 psig inspection during the restart from the current refueling outage.
3.
With respect to Request B in the referenced letter, the specific components-for which reliefis requested are:
Control Rod Drives:
14-19 22-51 14-47 46-39 22-35 42-43 The specific components listed above_were first inspected during the first-days of the outage, whilc the plant was at normal temperature and pressure.
No leaks were identified at that time. : Oyster Creek has not experienced ony cracking or corrosion on any CRD vessel flange bolts. The bolts used by Oyster Creek are of a lower hardness than the bolts which ~ have-exhibited cracking at other plants.
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