ML20094N885
| ML20094N885 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/31/1984 |
| From: | Parsons R CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| CON-NRC-251 165, NUDOCS 8408160437 | |
| Download: ML20094N885 (5) | |
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C9&L-Carolina Power & Light Company
~3 AB: gg P. O. Box 101, New Hill, NC 27562 July 31,-1984 Mr. James P. O'Reilly NRC-25!
United States Nuclear Regulatory Commission Region II 101 Marietta Street, Northwest (Suite 2900)
Atlanta, GA-30323 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT 1986 - 900,000 KW - UNIT 1 REACTOR VESSEL SUPPORT ANCHOR BOLT NUTS ITEM 165
Dear Mr. O'Reilly:
Attached is our second interim report on the subject item which was deemed reportable per the provisions of 10CFR50.55(e) on March 12, 1984. CP&L is pursuing this matter, and it is currently projected that corrective action and submission of the final report will be accomplished by October 2, 1984.
Thank you for your consideration in this matter.
Yours very truly, W
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. M. Parsons Project General Manager Shearon Harris Nuclear Power Plant RMP/j c=
1 Attachment cc: Messrs. G. Maxwell /R. Prevatte (NRC-SHNPP) i Mr. R. C. DeYoung l
OFFICIALCOPY 8408160437 840731 PDR ADOCK 05000400
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CAROLINA POWER'& LIGHT COMPANY S51EARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 SECOND INTERIM REPORT
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REACTOR VESSEL SUPPORT ANCHOR BOLT NUTS'
' ITEM 165 JULY 31, 1984 REPORTABLE UNDER 10CFR50.55(e)
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SUBJECT:
Shearon Harris Nuclear Pcwer Plant / Unit No. 1, 10CFR50.55(e) reportable deficiency. Anchor bolt nuts not properly secured on vertical and horizontal reactor vessel. support assemblies.
ITEM:
Two-vertical support anchor bolt nuts are loose and one nut is missing. Also, there are no washer material requirements given on design prints.
Several anchor bolt nuts on the' horizontal supports are not in full contact with the support structure, due'in part to a lack of thread on the bolt as well as to the angle at which the bolt projects through the assembly. Some bolts have washers, which are not required, and none have the half jam nut, which is required.
SUPPLIED BY:
Not a supplier-related deficiency.
NATURE OF DEFICIENCY:
Both the vertical and horizontal supports were designed as Seismic Class I assemblies.- The process control for complete installation and inspection of the reactor vessel supports was incomplete.
Procedures WP-119, Reactor Vessel Setting, and TP-28, Inspection of Equipment for Setting and Grouting, inadvertently failed to address post-grouting activities (e.g., final bolting and bolting inspection).
On the lateral supports, jam nuts were not installed. Some of the anchor bolts do not have sufficient threads to allow the nuts to come inv.o full contact with the supports. Washers were installed on some of the bolts but not on others, and the bolts in some cases vary from being perpendicular to the round surface of the supports, preventing full tightening of the bolts without the use of washers, which were not specified.
On the vertical supports, one nut was found missing and the material for the washers was not specified on a design document.
DATE PROBLEM OCCURRED:
March and April, 1980.
DATE PROBLEM REPORTED:
On March 12, 1984, CP&L (Mr. K. V. Hate') notified the NRC (Mr. A. Hardin) that this item was reportable per the provisions of 10CFR50.55(e).
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SCOPE OFr PROBLEM:.
. The hardware' deficiencies are limited to the reactor
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vessel supports. The program' deficiency potentially.
- affects all equipment on site installed prior ~to September 23, 1980.
SAFETY'
-IMPLICATION:
- The seismic strength'of'the supports is decreased by~
the missing and loose nuts and the improper bolt to support contact.
- REASON
-DEFICIENCY-IS REPORTABLE:
The' supports are for a Safety Class'I component.
CORRECTIVE ACTION:
- Procedure'TP-28, Revision 3, which incorporated the h
inspection for tightness of connections and
- fastenings,-was issued S,eptember 23, 1980. iThe
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installations and inspections of equipment after that date are considered adequate to ensure quality. The installations and inspections of the nuclear, safety-related and seismically-supported equipment i
installed prior to that date have subsequently been reviewed for similar problems, and no. deficiencies i
other than those reported for the reactor vessel were found.
Major NSSS equipment installation is primarily in accordance with procedures specifically written for 1
those items. The procedures for installing the reactor vessel, the steam generators, the reactor coolant pumps, and'the pressurizer have been reviewed and revised as necessary. The procedures, supplemented by the requirements of' Procedure TP-28 and WP-105, Installation and Inspection of Equipment, are considered adequate; therefore, installation and inspection activities are proceeding, j
An Exhibit 12 to Procedure WP-105 was prepared as a process control measure for the accomplishment of the necessary installation and inspection activities required to correct the reactor vessel support-l deficiencies. The required installation and inspection activities for the vertical supports has-been completed. The correction of the lateral
- support deficiencies will be completed following the installation and inspection of beveled washers i4 designed to provide full contact between the anchor i :
' bolt nuts'and the lateral' supports. The beveled-
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washers will eliminate the problem caused'by the 1
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unthreaded portions of the anchor bolts extending 1through the supports, and will permit tightening of the anchor bolt nuts in accordance with Field Change Request AS-4691. The beveled washers are presently being machined in accordance with Field Change Request AS-5281.
' FINAL REPORT: A final report will be issued following completion of the corrective actions stated above.
The revised projected issuance date for a final report on this item is October 2, 1984.
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