ML20078L722
| ML20078L722 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/22/1994 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C321-94-2209, NUDOCS 9411300391 | |
| Download: ML20078L722 (3) | |
Text
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-l GPU Nuclear Corporation Nuclear
= = = 888 Forked River New Jersey 08731-0388 609 971-4000 Wnter's Direct Dial Number:
November 22,1994 C321-94-2209 US. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 ASME Section XI Request for Relief R13 By letter dated October 25,1994, USNRC approved the Inservice Inspection (ISI) program for the Oyster Creek Nuclear Generating Station. This program was written to meet the 1986 edition of ASME XI, with no addenda.
Pursuant to 10 CFR 50.55a(a)(3), this letter is being written to request relief from specific requirements contained in ASME XI,1986 edition, Section IWA-5250(a)(2). This section of the Code refers to corrective action requirements relating to leakage from bolted connections.
The details and justification of this request are contained in Attachment I.
As restart from refueling outage 15R is presently scheduled for November 27,1994, expedited approval of this relief is requested by November 24,1994. If any further information or assistance is required, please contact Mr. John Rogers of my staff at 609.971.4893.
P John J. Bar m O
Vice President and Director Oyster Creek JJB/JJR Attachment cc:
Administrator Region I Senior Resident Inspector Oyster Creek NRC Project Manager 90 9411300391 941122 4d PDR ADOCK 05009219 P
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GPU Nuclear Corporation is a substd:ary of Genew Pubuc Utrues Corporation n[V I
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t-ATTACHMENT I RELIEE REQUESLR13 CODE
REFERENCE:
ASME Section XI 1986 edition, without addenda;
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IWA-5250(a)(2), CORRECTIVE MEASURES CODE REQUIREMENT:
If leakage occurs at a bolted connection, the bolting shall be removed as specified, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-3100 CODE RELIEF REQUEST.
1;or leakage found on Class I system bolted connections during the performance of the Class 1 system pressure test in refueling outage 15R, relief is requested as specified for the following bo!!ed connections:
A.
Main Steam Isolation Valve V-1-7, Body to Casing B.
Main Steam Isolation Valve V-1-8, Body to Casing C.
Recirculation Pump A, Pump to Pump Cover D.
Recirculation Pun.p C, Pump to Pump Cover E.
Local Power Range Monitor 20-49, Bolted Flange l
PROPOSED ALTERNATIVE EXAMINATION FOR REQUESTS:
For requests A,II,C, and D, a single bolt from the leakage path will be removed from the flange in question and a Section XI visual inspection performed prior to restart from the present 15R refueling outage.
For request E, no bolts will be removed for examination, as all of the bolts in this flange
]
were replaced with new, inspected bolts during 15R. There has been insufficient time for corrosion to develop, llASIS FOR RELIEF REQUESTS FOR A,B,C,and D Requests A, B, C, and D propose removing one bolt from the leakage path from each bolted flange in question. This proposed alternative examination is in compliance with the 1990 Addenda to ASME Section XI, subparagraph IWA-5250(a)(2).
T C321-94-2209 Attachment I Page 2 The examination of one bolt from the leakage path of a bolted flanged connection provides an acceptable level of quality and safety for the bolted connection. If any corrosion in excess of the limits specified in ASME Section XI,1986 edition with no addenda, paragraph IWA-3100 is detected on any bolt removed for this examination, then the remaining bolts in the flange will also be removed and examined ilASIS FOR RELIEF REQUEST E The bolts in the i.. ;ine flange for LPRM 20-49 were replaced with new bolts which were baseline examined during the current outage. Insufficient time has past to allow corrosion to occur.
SUSINIARY:
GPUN requests that the specified relief requested from the Code requirements be granted, as the major factors which can result in bolt corrosion (and were discussed in GPUN letter C321-93-2041 dated February 4,1993) are: 1) not applicable to Oyster Creek (such as chemically accelerated corrosion); 2) under control by existing procurement and examination programs (such as the quality assurance requirements for procurement and the existing ISI requirements for examination); 3) not existent at Oyster Creek as evidenced by extensive operating history, controlled maintenance procedures, and inservice inspection records compiled since 1969.
Additionally:
Requests A,II,C and D comply with the NRC approved 1990 Addenda to ASME.
Request E addresses new bolts which were baseline examined less than two months ago.