3F1085-05, Submits Response to 850826 Request for Addl Info Re Generic Ltr 83-28,Items 4.2.1 & 4.2.2.Preventive Maint Procedure PM-118 Will Be Performed on 12-month Basis Per B&W Owners Group ATWS Committee Recommendations

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Submits Response to 850826 Request for Addl Info Re Generic Ltr 83-28,Items 4.2.1 & 4.2.2.Preventive Maint Procedure PM-118 Will Be Performed on 12-month Basis Per B&W Owners Group ATWS Committee Recommendations
ML20133G697
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 10/11/1985
From: Westafer G
FLORIDA POWER CORP.
To: Stolz J
Office of Nuclear Reactor Regulation
References
3F1085-05, 3F1085-5, GL-83-28, NUDOCS 8510160085
Download: ML20133G697 (2)


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e++.e Florida Power C0RPORATf0N October 11,1985 3F1085-05 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20535

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Request for Additional Information Generic Letter 83-28, Items 4.2.1 and 4.2.2

Dear Sir:

Florida Power Corporation (FPC) is submitting this response in accordance with your August 26,1985 (3N0885 24) letter as modified by our September 25, 1985 (3F0985-22) letter.

FPC will perform preventative maintenance procedure PM-Il8 on a twelve-month basis in accordance with B&W Owners Group ATWS Committee recommendations.

On a monthly basis, FPC will perform a functional test (surveillance procedure SP-110, Technical Specification reference 4.3 and 4.10) which ensures that reactor trip breakers are functioning properly.

The six maintenance items requested in your letter will be included in maintenance procedure PM-ll8. Items 1, 4, 5, and 6 listed below will be included.

by October 31, 1985. For item 2, FPC will continue to perform the armature measurement practice currently specified in maintenance procedure PM-ll8 until B&W provides the necessary guidelines. For item 3, verification of trip response time will be performed once a year as part of maintenance procedure PM-Il8.

This frequency is recommended in the Generic Preventative Maintenance and Surveillance Instructions for G.E. AK 2/2-15/25 reactor trip breakers, incorporating Post-Salem Test and Operating Experience (Doc. #51 1157077-00).

Listed below are the six maintenance items.

1. Verification of breaker physical condition, including wiring insulation and termination, all retaining rings, pole bases, are quencher, stationary and movable contacts, and tightness of nuts and bolts.

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$kO$00$ 0 P i GEN ERAL OFFICE 3201 Tnirty-fourth street south e P.O. Box 14042, st. Petersburg, Florida 33733 e 813-866-5151

October 11,1985 3F1085-05 Page 2

2. Verification of the optimum freedom of the armature as specified in General Electric Service Advice 175-9.35, Item #St.
3. Verification of proper trip response time as specified in Service Advice 175-9.35, item #S6.
4. Lubrication of trip shaft and latch roller bearings with Mobil 28 lubricant.
5. Examination and cleaning of breaker enclosure.
6. Functional test of the breaker prior to returning it to service. ,

B&W has agreed to collect, compile, and trend data for reactor trip breaker response time, trip shaf t torque, under voltage device (UVD) pickup voltage, and UVD dropout voltage. Trends will be generated for CR-3 individual breakers and for B&W plants as a group. Any anomolles observed in CR-3 trends or group trends will be evaluated and appropriate recommendations will be made. Reports are planned to be issued on a semi-annual basis depending on the amount of data received. Information on failures occurring during a reporting period will be included in the reports.

FPC Nuclear Operations Engineering will compile and submit to B&W the trend data information outlined above annually as a minimum through the completion of the B&WOG program. B&W will perform the analysis as described in the preceding paragraph.

Sincerely, n

I G. R. Westafer Manager, Nuclear Operations Licensing and Fuel Management EMG/feb

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