AECM-83-0605, RO 83-084/0:on 830819,during Performance of Fire Protection Surveillance procedure,16 of 20 Q-rated Fire Dampers Discovered W/S Shaped Hooks Connecting Fusible Links W/Damper Instead of Required vice-crimped Straps

RO 83-084/0:on 830819,during Performance of Fire Protection Surveillance procedure,16 of 20 Q-rated Fire Dampers Discovered W/S Shaped Hooks Connecting Fusible Links W/Damper Instead of Required vice-crimped Straps

ML20080M034
Person / Time
Site:	Grand Gulf
Issue date:	09/21/1983
From:	Dale L MISSISSIPPI POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
AECM-83-0605, AECM-83-605, RO-83-084-0, RO-83-84, NUDOCS 8310030430
Download: ML20080M034 (2)

Text

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.c MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi EdMEMiddB P. O. B O X 16 4 0, gl4f2 O N , MISSISSIPPI 39205

$ ek ber 21, 1983 NUCLEAR PRODUCT 1oN DEPARTMENT U.S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30303 Attention: Mr. J. P. O'Reilly, Regional Administrator

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-13 File: 0260/L-835.0 Special Report 83-084/0 - Discovery of Incorrect Connectors Installed Between Fusible Links and Q-Rated Fire Dampers AECM-83/0605 On August 19, 1983, during the performance of an eighteen month fire protection surveillance procedure, it was discovered 16 out of 20 Q-rated fire dampers used "S" shaped hooks to connect the fusibic links with the damper instead of the required vice crimped straps.

The incorrect connectors were installed as an oversight by construction.

The S-hooks are specified for use only in non-Q dampers. The S-hooks would not have prevented the fire dampers from closing during a fire, although it is possible the open end of the S-hooks could allow the linkage to separate during a major seismic event. This would allow the dampers to close, thereby shutting off its part of ventilation to specific ESF equipment.

The S-hooks have been removed and replaced with vice crimped straps per specifications.

This is reported pursuant to Technical Specification 3.7.7. There was no ef fect on the health or safety of the public nor was there a threat to plant safety. This is a final report.

Yours truly, j

4 L. F. Dale Manager of Nuclect Services EBS/SHH:rg

.pt C$

O cc: See next page 8310030430 830921 gDRADOCK05000g

/[dyb Member Middle South Utilities System

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- AECM-83/0605

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MIIl321PPI POWER Q LI2HT COMPANY cc: Mr. J. B. Richard Mr. R. B. McGehee Mr. T. B. Conner Mr. G. B. Taylor Mr. Richard C. DeYoung, Director Office of Inspection & Enforcement-U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i

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.o, . .. .o . co,,.. HARTFORD, CONNECTICUT 06141-0270 g Nonnease uws se=ca cew= (203) 666-6911 NONb4ARY NuCLlam thtmov Coww September 22,1983 Docket No. 50-245 B10894 Director of Nuclear Reactor Regulation Attn: Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch //5 U. S. Nuclear Regulatory Commission Washington, D. C. 20555

References:

(1) W. G. Coi.nsil letter to D. M. Crutchfield, dated October 15, 1980.

(2) B. H. Grier letter to W. G. Counsil, dated February 12,1981.

Gentlemen:

Millstone Nuclear Power Station, Unit No.1 Integrated Primary Containment Leak Rate Testing In Reference (1), Northeast Nuclear Energy Company (NNECO) proposed changes to the Millstone Unit No. 1 Technical Specifications which would allow termination of the integrated primary containment leak rate test (IPCLRT) in less than the currently specified 24-hour period. In Reference (1) we noted that we requested Region I to determine appropriate criteria for terminating the IPCLRT. Region I responded with Reference (2), which forwarded acceptance criteria for an IPCLRT duration of less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Our IPCLRT procedure conforms to the Bechtel Topical Report, BN-TOP-1, Revision 1, dated November 1,1972, and otherwise conforms to the acceptance criteria contained in Reference (2). We are currently planning to conduct an IPCLRT during our upcoming refueling outage, and request that the proposed change in Reference (1) be reviewed with that schedule in mind. Please contact us if you have any questions or require any other assistance.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY W,b. Ow W. G. Counsil Senior Vice President

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By: C. F. Sears g g Vice President Nuclear and i Environmental Engineering 8310030428 830922 PDR ADOCK 05000245 P PDR