ML17249A363
| ML17249A363 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/07/1979 |
| From: | White L ROCHESTER GAS & ELECTRIC CORP. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-02, IEB-79-2, NUDOCS 7912280022 | |
| Download: ML17249A363 (10) | |
Text
V II5 ROCH ES TER GAS AND ELEC TRIC CORPORA TION
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S9 EAST AVENUE, ROCHESTER, N.Y. 14649 LEON D. WHITE, JR.
VICE PRC5IDCNT TC LC P H0 44 C
- RCA COOC TI5 546-2700 December 7,
1979 Mr. Boyce -H. Grier, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, PA 19406
Subject:
IE Bulletin No. 79-02, Revision 2
Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts R. E. Ginna Nuclear Power Plant, Unit No.
1 Docket No. 50-244
Dear Mr. Grier:
Enclosed is a copy of our response to the subject IE Bulletin.
Very truly yours, Enclosure xc:
U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, DC 20555
Revised
Response
to IE Bulletin No. 79-02 Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts R.E. Ginna Nuclear Power Plant, Unit No.
1 Docket No. 50-244 Introduction The Nuclear Regulatory Commission, Office of Inspection and Enforcement, issued Revision 2 to IE Bulletin No. 79-02 on November 8, 1979, to clarify the intent of the Bulletin and establish NRC positions concerning minimum factors of safety, anchor bolt preload and the expected date of completion for certain Bulletin actions.
A report was required within 30 days of the Bulletin Revision issue date.
The remainder of this revised response comprises Rochester Gas and Electric Corporation's (RG&E) report.
Res onse to Action to be Taken b Licensees and Permit Holders Pi e Su ort Base Plate Flexibilit 2.
Item 1 of Action to be Taken by Licensees and Permit Holders addresses consideration of pipe support base plate flexibility. This subject was fully addressed in reports dated July 6,
- 1979, and July 26, 1979.
Minimum Factor of Safet 3.
Item 2 of Action to be Taken by Licensees and Permit Holders addresses minimum factors of safety for concrete expansion anchor bolts.
This subject was fully addressed in reports dated July 6,
- 1979, and July 26, 1979.
C clic Loads Item 3 of Action to be Taken by Licensees and Permit Holders addresses design requirements for anchor bolts to withstand cyclic loads.
This subject was fully addressed in the report dated July 26, 1979.
C Documentation Item 4 of Action to be Taken by Licensees and Permit Holders addresses verification from existing QC documentation that design requirements have been met for each anchor bolt in certain areas.
The testing and replacement program for load bearing pipe support base plate designs using concrete anchor bolts was described in the reports dated July 6, 1979 and July 26, 1979.
A testing program for supports using structural steel shapes has been initiated.
For shell type expansion anchor bolts, the testing program uses a direct loading method to ascertain the adequacy of bolt installation.
For wedge type expansion anchor bolts, the testing program uses a torque method.
Ex ansion Anchor Bolts Used in Concrete Block Walls Item 5 of Action to be Taken by Licensees and Permit Holders addresses expansion bolts used in concrete block walls.
During work performed to develop previous responses to IE Bulletin 79-02, four supports in the discharge line from the turbine driven auxiliary feedwater pump were found to have expansion anchor bolts in concrete block walls.
These supports were redesigned to eliminate use of expansion anchor bolts and modifications were completed prior to issue of Revision 2 to IE Bulletin 79-02.
Pi e Su orts with Ex ansion Anchor Bolts Usin Structural Steel Sha es Item 6 of Action to be Taken by Licensees and Permit Holders addresses the use of expansion anchor bolts with pipe supports having structural steel shapes rather than base plates.
a ~
b.
c ~
Attachment 1 to this report presents a revised list of systems involved and numbers of supports.
Systems and portions of systems within the scope of IE Bulletin 79-02.are defined by Sections 1.a and 1.b of RGBs July 26, 1979 report.
As work progresses in accordance with this revised Bulletin, the list will be verified and the additional data required (type of anchor bolt and line size) will be generated.
The subject of adequacy of anchor bolt design was fully addressed in our reports dated July 6,
- 1979, and July 26, 1979.
Our reviews to date have not uncovered any basic design problems with anchor bolts in other structural shapes.
As stated in our July 6, 1979 response, it is not possible to reanalyze supports within the scope of IE Bulletin 79-02, Revision 2, to verify anchor bolt loads prior to initiation of the testing program described in Item c below.
In addition, other reviews are presently in progress for the Systematic Evaluation Program which
- will probably result in changes to calculated pipe support loads.
Therefore, RG&E has developed a program for complete reanalysis of all Seismic Category I pipe supports on piping systems 2 inch nominal size and larger; including the concerns of this Bulletin relative to flexibilityand anchor bolt loadings.
The schedule for completion of this work will be consistent, with the dates established for the seismic review of piping systems under the Systematic Evaluation Program.
d.
A program is currently in progress to test anchor bolts in pipe support, designs (see Attachment 1 to this report) using structural steel shapes.
This program includes'those systems and portions of systems within the scope of IE 'Bulletin 79-02 as defined by Sections 1.a and 1.b of RG&E's July 26, 1979 report.
The first phase of this program has been developed to permit testing and evaluation of affected accessible supports outside containment, and performance of any necessary corrective action, prior to March 1, 1980.
A second phase of the program will be placed into effect during the Spring 1980 refueling outage to accomplish the same goals for 'affected supports inside containment and in areas that are not accessible during normal operation.
This second phase will be completed prior to the end of the Spring 1980 refueling outage.
Schedulin Item 7 of Action to be Taken by Licensees and Permit Holders requires a schedule for completion of Items 1, 2, and 4.
These items have been fully addressed in reports dated July 6,
- 1979, and July 26, 1979.
The program outlined therein has been completed except; for 10 inaccessible sup-ports in the chemical and volume control system.
These supports will be completed during the Spring 1980 refueling outage.
Documentation and Re ortin Documentation and reporting requirements of Item 8 of Action to be Taken by Licensees and Permit Holders will be satisfied by RG&E.
Item 5 has been completed as stated above.
Work to complete Item 6 is in progress as stated. above.
Item 7 has been addressed in previous reports (July 6,
- 1979, and July 26, 1979).
Items 2 and 4 have also been addressed previously as stated above.
Action for Holders of Construction Permits Item 9 of Action to be Taken by Licensees and Permit Holders is not applicable to Ginna Station.
ATTACHtKNT 1 REVISED LIST OF SUPPORTS USING STRUCTURAL STEEL SHAPES
~sstem Reactor Coolant Total Number of Su orts Number Numbers N~$ ~
Accessible Accessible 0
-5 Main Steam Main Feedwater Standby Auxiliary Feedwater Safety Injection Residual Heat Removal Containment Spray Chemical and Volume Control Component Cooling Service Hater Steam Generator Blowdown Auxiliary Feedwater 83 53 31 110 33 83 51 29 29 7
15 (3) 20 0
TOTALS 373 313 60 Notes:
1.
List is revised from that submitted by letter from Mr. B. A. Snow to Mr. B. H. Grier of NRC on October 3, 1979.
2.
Not accessible indicates inside containment, except for CVCS.
3.
Ten supports are inside containment, five are in inaccessible areas outside containment.
I