ML17244A779

Forwards Supplemental Response to IE Bulletin 79-02 Re Pipe Support Base Plate Designs Using Concrete Expansion Bolts. Submits Info Re Testing & Replacement Program,Base Plate Flexibility & Replacement Program

ML17244A779
Person / Time
Site:	Ginna
Issue date:	07/26/1979
From:	White L ROCHESTER GAS & ELECTRIC CORP.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 7908230107
Download: ML17244A779 (18)

Text

QP I,!!!!!!! ililusisii!Z ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 74649 I.CON D. WHITE. JR. TEI.EPHONE VICE PRESIDENT AREA COOE llS 546.2700 July 26, 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 Sub j'ect

Supplemental Response IE Bulletin No. 79-02 Pipe Support Base Plates Designs Using Concrete Expansion Anchor Bolts R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244

Dear Mr. Grier:

On July 6, 1979 we provided you with a response to the subject, IE Bulletin. During subsequent discussions with members of the Region 1, IE Headquarters, and DOR Staff we have been requested to provide additional information concerning our initial response. Enclosed is a copy of the information requested.

Very truly yours, r

L. D. Whi , Jr.

Enclosure zc: U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, DC 20555 T. 908S30 Q7

0 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

1. ~sstems a) The following is a list of'he systems, and portions of systems, included in Phase 1 of our testing and replace-ment program; and the number of supports in each. These systems are the essential Seismic Category I systems required for reactor coolant system integrity and achieving a safe. shutdown condition following a seismic event. In addition, the list includes those systems necessary to mitigate the consequences of a design basis loss of coolant accident. This list of systems has been developed for Systematic Evaluation Program Topics VII-3, "Systems Required for Safe Shutdown"; and III-1, "Classification of Structures, Components, and Systems".

Reactor Coolant System 1 Main Steam 0 Main Feedwater 0 Standby Auxiliary Feedwater 19 Safety Injection System Residual Heat Removal 15 Containment Spray 0 Chemical and Volume Control System 15 Component Cooling System 10 Service Water 17 Steam Generator Blowdown 1 Total 82 b) The following is a list of the systems, and systems, included in Phase 2 of our testing portions of and replace>>

'ent, program. These systems are designated Seismic Category I but are not required for reactor coolant syst: em integrity, achieving a safe shutdown condition following a seismic event, or mitigating the con-sequences of a loss of coolant accident.

Auxiliary Feedwater 21 Boric Acid System 10 Chemical and Volume Control System 5 Service Water 9 Total 45 c) Both phases of our testing and replacement program include load bearing pipe support base plate designs using concrete expansion anchor bolts. The program has been revised to include anchor bolts in load bearing pipe support base plate designs on all 2@ inch and critical 2 inch nominal size piping systems on the above lists.

2. Base Plate Flexibilit a) As indicated in our initial response on July 6, 1979, was not possible to reanalyze, using flexible plate it assumptions, the base plates on all pipe supports in our testing and replacement program prior to its initiation.

,Therefore, a representative sample of 10 typical pipe

'support; base plates has been analyzed, using rigid plate assumptions, for both existing and replacement designs.

The results of these analyses are shown in Table 1. In all cases, bolt capacity has been increased in the replace-ment; designs. In 2 cases (SWAH-19 and SWAH-23), additional.

analyses, using flexible plate assumptions, have been performed. These analyses show minimum factors of safety of 5.00 and 5.35, respectively, for the replacement designs. The design factor of safety for the wedge type anchor bolts used, in the replacement designs is 4.00.

I't is our determination that the design bolt capacities provide sufficient margins of safety to account for any load increases due to flexibility.

b) In general, pipe supports at Ginna Station with base plates using concrete expansion anchor bolts are of similar design.

Figures 1 through 5 show the design of the supports described, above. They are typical of the type used in Seismic Category I systems throughout the plant.

3. Schedule The schedule for the anchor bolt testing and replacement program described in our July 6, 1979 response has been accelerated. The testing and replacement of all anchor bolts in inaccessible and accessible supports included in Phase 1 will be completed prior to August 1, 1979. Phase 1 includes all the systems listed in paragraph 1(a) above. This revised schedule is consistent with our plans for returning the plant to power operation following the present outage to perform the inspections and repairs required by IE Bulletin 79-13.

'I TABLE 1 Existing Design Replacement Design Support No. Bolt Load Bolt Capacity Factor of-Safety Bolt Load Bolt Capacity Factor of Safety Tension Shear Tension Shear Tension Shear Tension Shear ACH"106 75 0 7285 5760 97.0 75 0 14100 15195 188.0 ACH-118 241 293 7285 5760 11.9 241 293 14100 15195 27.5 SWAH-19 3161 1435 26880 26880 5.8 1452 957 14100 15195 6.0 SHAH-23 2963 1345 26880 26880 6.2 1257 -

897 14100 15195 6.8 SHAH-24 1972 895 26880 26880 9.4 837 597 14100 ,15195 10.1 SWCH-63 6 0 7285 5760 1121.0 0 11550 15195 1650.0 SWCH-73 18 0 7285 5760 399.0 19 0 11550 15195 608.0 SWCH-74 14 0 7285 5760 520.0 14 0 11550 15195 825.0 ACH-100 262 0 7285 5760 27.8 340 ~126 14100 15195 30.9 SWAH-37 499 220 7285 5760 9.4 455 250 14100 15195 20.5

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