ML20198R703
| ML20198R703 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/28/1986 |
| From: | Shell R TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8606100176 | |
| Download: ML20198R703 (8) | |
Text
{{#Wiki_filter:- -.. we o TENNESSEE VALLEY AUTHORITY CHATTANQOGA. TENNESSEE 37401 9l.5%156BLookoutPlace 1 %\\ May 28, 1986 U.S. Nuclear Regulatory Commission Region II ATTN: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
Dear Dr. Grace:
SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 - NRC-OIE REGION II INSPECTION REPORT 50-327/86-17 AND 50-328/86 COMMENTS ON PRESTART TRAINING ITEMS Enclosed are our coments in regard to J. A. Olshinski's Apell 28, 1986 letter to S. A. White which transmitted IE Inspection Report Nos. 50-327/86-17 and 50-328/86-17 for our Sequoyah Nuclear Plant. In the referenced letter TVA was requested to notify NRC if we did not concur with NRC's statement of prestartup training commitments as listed in section 9 of the subject report. We have reviewed this information and our comments are presented in enclosure 1 with our commitments listed in enclosure 2. We do not recognize any other actions described herein or the subject inspection report as commitments. If you have any questions, please set in touch with R. E. Alsup at FTS 858-2725. To the best of my knowledge, I declare the statements contained herein are complete and true. Very truly yours, TENNESSEE V LLEY AUTHORITY / R. H. Shell, Supervisor Licensing Project II Enclosures cc: Mr. James Taylor, Director (Enclosures) office of Inspection and Enforcement U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Mr. S. P. Weise, Chief Reactor Projects Branch 1 Division of Reactor Projects U.S. Nuclear Regulatory Commission Region II - Suite 2900 101 Marietta Stree, NW Atlanta, Georgia 30323 8606100176 860528 PDR ADOCK 05000327 O PDR An Equal Opportunity Employer
't ENCLOSURE 1 COMMENTS - NRC INSPECTION REPORT NOS. 50-327/86-17 AND 50-328/86-17 J. A. OLSHINSKI'S LETTER TO S. A. WHITE DATED APRIL 28, 1986 1. NRC Statement Ensure that each licensed operator completes a simulator reactor startup as part'of requalification training. Operators presently attending college full-time would be exempted from this prestartup commitment. (This exemption does not apply to annual requirements for reactor startups and reactivity manipulations.) TVA Comment This action was completed with each licensed operator completing a simulator reactor startup during the cycle 1 requalification conducted January - February 1986. 2. NRC Statement Provide a training letter to all operators on major plant modifications completed during the extended outage. TVA Comment TVA concurs with this statement of commitment. A training letter will be issued before startup. 3. NRC Statement Provide a training letter regarding precautions to be taken on a unit startup with a high boron concentration and potential positive moderator temperature coefficient. TVA Comment NRC stated that this would be required because of the present fuel configuration in unit 2. This condition is not applicable to unit 2, but is applicable to unit 1. Therefore, the subject training letter will be issued for startup of unit 1. The commitment should now read, " Provide a training letter regarding precautions to be taken for unit 1 startup with a high boron concentration and potential positive moderator temperature coefficient." 4. NRC Statement If the Unit 2 startup does not occur prior to requalification cycle 2 in May, additional simulator training startups would be conducted for all licensed operators except for those attending college. If the startup occurs prior to this requalification cycle, the licensee committed to provide additional simulator trainine for licensed personnel assigned to the shifts responsible for Ehe startup.
l TVA Coment Requalification cycle 2 was completed the week of April 28, 1986. This included simulator training of heat up and cool down. TVA will provide additional startup simulator training for licensed employees who will be involved in the unit'2 startup. J Additional Coments Please note that section 9 states ". . the present fuel configuration in Unit 2, which is the first unit to restart, will require a very high initial boron concentration." Although we do anticipate that unit 2 will be the first unit to restart, the fuel configuration applies to unit 1 and not unit 2, as stated. This is reflected in the coment to item 3 above. The inspection report also stated NRC concerns related to nonlicensed operator requalification training. Specifically, only one week of retraining was provided annually and appeared to be utilized for annual retraining requalifications, such as general employee training, fire fighting training, and emergency planning. We do not believe that this is a corre..'. assessment of the requalification program. As shown by the attached outlines of the Auxiliary Unit Operator (AUO) requalification programs for 1984, 1985, and 1986, the week-long programs are not utilized for those subjects specified by NRC, but are instead used to keep the AUOs up-to-date on issues specifically related to job performance. In addition, a second week has been added to the annual requalification program. Specific topics of the second week have not yet been developed. The second week is expected to be completed in October or November 1986. l I i f 1 I a .----,.---e-.--n. -.._.---,.--.--,--,-,.n.- -.-n.
ENCLOSUR3 2 COMMITMENTS 1. By startup all operators will be provided with a training letter on major plant modifications completed during the extended outage. 2. By unit 1 startup the unit 1 operators will be provided with a training letter 'regarding precautions to be taken on a unit startup with a high boron concentration and potential positive moderator temperature coefficient. 3. By unit 2 startup TVA will provide additional startup simulator training for licensed employees who will be involved in the unit 2 startup. l l t I i V
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ATTACHMENT SEQUOYAH NUCLEAR PLANT Page 1 of 2 1984 AUO REQUALIFICATION 4/11/84 INDEX j DAY 1 A. New and Old Steam Generator Blowdown System B. Plant Modifications (ECNs Completed During Unit 2's Refueling Outage) C. Fuel Handling V T,; DAY 2 A. Makeup Demineralizer Plant Operation 2 2 B. H /0 Analyzer Operation and Tech Spec Consideratio'ns C. RWP and Protection Against Radiation Exposure (RCI 1,13 and 14) ~ D. Plant Safety (HCIs) h -{-
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DAY 3 A. Maintaming Plant Awareness and System Operational Status 1. Log Entries AI-6 f[,5 2. Proper Method of Reviewing Valve Checklist . ~.. 3. Feedwater Reg Valve Dogs - 1. 4. Shift Relief s. .e .~; B. Surveillance Instructions (SI) 1. SI-1 s C. Anticipated Transients Without Scram ATWS (EOI-14) 1. Purpose of EOI-14 2. Responsibility of AUO T D. Maintenance Requests (MRs) ...,, 'l 1. Proper Completion of MRs
SEQUOYAH NUCLEAR PLANT Page 2 of 2 1984 AUO REQUALIFICATION 4/11/84 INDEX DAY 4 A. Placing Nos. I and 2 Heaters in Service (GOI) B. Unit Station Service 1. 6.9kV and 480V Bds 2. Typical Feeds y C. Local Operation of Steam Driven AunHary Feedwater Pumps s. D. Diesel-Generator Starting Air and Fuel Oil ~ System DAY 5 A. Licensed Event Reports and Significant Evenfi Reports 'c B. Suggestions and Discussion of Problem, g_ _. I C. Review .s.i D. Quiz k e't -= .ej u ..?, : 4 y
A SEQUOYAH NUCLEAR PLANT AUO REQUALIFICATION TRAINING 1985 TABLE OF CONTENTS DAY l A. AUO Annual Retraining Requirements gg B. Maintaining Awareness of Plant and System Operational Status C. Procedure Changes . r 'D. Unit 2 Cycle 2 Modifications and Cooling Tower Operation. E. Steam Generator Layup Water Treatment Recirculation System F. Steam Generator Blowdown System DAY 2 A. Water Chemistry and Plant Operations -h B. Radwaste Release from SQN Liquid and Gas DAY 3 A. Condensate Demineralizer Waste Evaporator d4s ..; J ' B. Radiation Monitoring at SQN a DAY 4 A. Auxiliary Feedwater System B. Waste Gas Compressors and Gas Decay Tanks a C. Makeup Demineralizer System DAY 5 -3 SQN Violations and Reportable Occurrences for 1984 0
1986 AUO Requal Day 1 : Maintaining Awareness of the plant and system operation status Control Room Inaccessibility Day 2 : York Chillers j V Heater Drains and Vents 3, - r-5 -Day 3 : Unit 1&2 Outage Modifications Sullair Compressor Day 4 : CDWE Modifications .. Auxiliary Boiler and Auxiliary Steam Systems m . ;f. t e Day 5: Industry Events Reveiv -QUIZ ~,
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