ML20247C426

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Forwards Response to Request for Addl Info Re Torus Support Column Rock Bolts.Calculation Sheets Encl
ML20247C426
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 03/23/1989
From: Hairston W
GEORGIA POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247C432 List:
References
HL-383, NUDOCS 8903300190
Download: ML20247C426 (21)
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W :, AG e : /. ] rr e t Q :w k < ;; y & C:' ,e H ~ o 'J C w:r gr y* A>,i , :a ' %9 ,,. rr W. G. Hairston, Hi r Vic t h-;., A r.1 'e r nm ana.,. HL-383 0049V X7GJ17-H720 March 23, 1989 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 TORUS SUPPORT COLUMN ROCK BOLTS Gentlemen: On December 1, 1988, Georgia Power Company (GPC) met with NRC representatives from Nuclear Reactor Regulation (NRR) and Region II regarding the angular deflections identified in the Unit 1 torus mitre joint support column rock bolts. The subject rock bolts are used to restrain the torus under postulated containment uplift loads. Based on the presentations made during the meeting, it was concluded that the undeflected and slightly deflected rock bolts would be able to withstand the postulated uplift loads and hence, containment integrity would be maintained. Therefore, there was no immediate safety concern and continued operation of the unit was justified. At the conclusion of the meeting, GPC committed to document the results of our evaluation and submit it to the NRC. Also, on December 14,

1988, the staff transmitted, by
letter, a

series of questions associated with containment and rock bolt integrity. Enclosure 1 presents the responses to these questions. Note that GPC plans to submit a revision to the Plant Unique Analysis Report (PUAR) by the end of 1989. The PUAR is the licensing basis report which documents the adequacy of the Plant Hatch containment, as evaluated during the Mark I Long Term Containment program. I 8903300190 890323 h g ADOCK0500g1 y PDR P e i

f k L U.S.-Nuclear Regulatory Commission i March 23, 1989 Page.Two He trust that the enclosed'information satisfies your needs. Please contact this office if you have questions. Sincerely, g).jb. ll A H. G. Hairston, III GKM/eb

Enclosures:

1. Request for Additional Information on Bent Torus Rock Bolts - Hatch Unit 1 2. "E. I. Hatch Nuclear Plant Unit 1 Suppression Chamber Support Anchor Bolt Study," dated March 1989. c: Georaia Power Company Mr. H. C.. Nix, General Manager - Hatch Mr. L. T. Gucwa, Manager h'uclear Engineering and Licensing - Hatch G0-NORMS U.S. Nuclear Reaulatory Commission. Washinaton. D.C.- Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Regulatory Commission. Reaion II Mr. S. D. Ebneter, Regional Administrator Mr. J. E. Mer.ning, Senior Resident Inspector - Hatch ___________m 'I

6 7 1' ENCLOSURE 1 REQUEST FOR ADDITIONAL INFORMATION. BENT TORUS ROCK BOLTS HATCH UNIT 1 NRC OUESTION l' Provide copies of existing documents related to: I-a. Analysis and test of rock bolts, b. Detailed' calculations for weld shrinkage, c. Torus load reduction.

d. ; Calculation of loads on columns with bent bolts.

e. Calculations of rockbolt capacity.

RESPONSE

The response to these items is contained in sections'III through VI in the suppression chamber. support anchor bolt study. The original loads and capacities for items c,. d, and e are provided in Bechtel Calculation L-254.0 (pages 149 through 151 and 168 through 180) which is provided in this enclosure. NRC OUESTION 2 Provide information related to the pullout capacity of the-bolts, with - proper consideration of the.following: a. The capacity of the bolts calculated by GE (230 kips) is much higher than the vendor-recommended design capacity (155 kips). b. If some of the nuts and washers have come through rotation, recompute the lateral load on the bolts (at outriggers) and axial loads considering the appropriate preload on the bolts. c. Consider appropriate ratchetting effects of the bent bolts in the grout and concrete. l I l 0049V I HL-383 El-1 j

l l e 4 ENCLOSURE 1 (Continued) REQUEST FOR ADDITIONAL INFORMATION BENT TORUS ROCK BOLIS HATCH UNIT 1

RESPONSE

The response to Question 2.a is contained in the Suppression Chamber Support Anchor Balt Study, Section IV and in Bechtel Calculation L-254.0 (pages 178 through 180). The capacity of the deflected rock bolts is determined by testing and fracture mechanics formulations. It should be noted that the vendor recommended capacity of 155 kips represents a value utilized in commercial applications. Load capacities recommended by vendors may be increased based on testing, proper consideration of load phenomenon and analysis. s The response to Question 2.b is contained in the Suppression Chamber Support Anchor Bolt Study, Section IV. The response to question 2.c is contained in the Suppression Chamber Support Anchor Bolt Study, Section VI (Bechtel Calculation L 254-3, page 20). NRC OUESTION 3 Relate the actual shrinkage of the major radius of the torus to the calculated shrinkage.

RESPONSE

The response to this time is contained in the Suppression Chamber Support Anchor Bolt Study, Section III. NRC OUISTION 4 The amount of weld shrinkage indicates that there would be substantial restraining stresses in the shell (longitudinal and transverse). If not considered in the existing document (i.e., item 1), consider these stresses in determining the shell integrity under various load combinations.

RESPONSE

This item was evaluated prior to the meeting on December 1, 1989. The response is contained in the Suppression Chamber Support Anchor Bolt Study, Section VI (Bechtel Calculation L-254.3). l 0049V HL-383 El-2

ENCLOSURE 1 (Continued) REQUEST FOR ADDITIONAL INFORMATION ENT TORUS ROCK BOLTS - HATCH UNIT 1 NRC OUESTION S Provide plans to periodically check the rockbolt positions 'and the condition of the rockbolt anchorages in the concrete.

RESPONSE

Georgia Power Company will. implement a procedure providing for visual inspections once per operating cycle. Inspection results will be evaluated to increase or decrease the inspection. frequency as appropriate. .-ORIGINAL LOAD CALCULATIONS The following pages present the original Bechtel load calculations in response to portions of NRC Ouestion 1. 1 l^ 0049V HL-383 El-3 L_____--------

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