Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared TrolleyML20247N229 |
Person / Time |
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Site: |
Sequoyah |
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Issue date: |
05/26/1989 |
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From: |
Office of Nuclear Reactor Regulation |
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To: |
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Shared Package |
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ML20247N226 |
List: |
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References |
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RTR-NUREG-0612, RTR-NUREG-612 NUDOCS 8906050273 |
Download: ML20247N229 (3) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
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[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
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I i i
/ 'o g UNITED STATES NUCLEAR REGULATORY COMMISSION 5 p WASHINGTON, D. C. 20655 e \"..../ .
ENCLOSURE-SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION !
I REVISION TO THE HEAVY LOAD CONTROL COMMITMENTS SEQUOYAH UNITS 1 AND 2 TENNESSEE VALLEY AUTHORITY DOCKET N05. 50-327/328
1.0 INTRODUCTION
In NUREG-0612. " Control of Heavy Loads at Nuclear Power Plants," dated July 1980, the staff provided guidelines for the control of heavy loads. Based on the staff's review of the licensee's commitments provided in its submittals, the staff issued its safety evaluation for Sequoyah (SQN), Units 1 and 2, in a letter from T. Novak (NRC) to H. G. Parris (TVA) dated March 26, 1985. Therein, the staff concluded that the guidelines of NUREG-0612 had been satisfied at SQN.
Upon performing' additional euluations in'to the comitments that were originally made in SQN's NUREG-0612 submittals (Reference 4.1), TVA determined that three of the comitments should be deleted. They are heavy load control on 5-ton electric monorail hoist with integral trolley, 4-ton monorail chain hoist with geared trolley, und 3-ton jib crane with 3-ton wire rope electric hoist and chain-driven trolley. The staff's evaluations of these three changes to the heavy load commitments are discussed below.
2.0 EVALUATION ;
e
'2.1 Item 4 (Reference 4.1) "5-Ton Electric Monorail Hof st With Integral Trolley" Commitment , ,k TVA originally comitted to initiate a design change request (DCR) to locate trolley stops on the 5-ton monorail above the evaporator feed filter to provide e a safe load path. '
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Revised Response The load handled by this hoist is the concrete plug for the waste evaporator feed filter. This plug is 29 inches square, and the concern was that it could poten-
- ially be lifted near the residual heat removal (RHR) room cooler supply control valve and the RHR pump A-A minimum flow valve switch. -
Licensee's examination of the calculations for the plug shows that the weight of the plug is 1,789 pounds. The heavy load is defined as any load, carried in a given area after a plant becomes operational, that weighs more than the combined weight of a single spent fuel assembly and its associated handling tool for the
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. 2- l specific plant in question. According to Technical Specification Change 87-41, 2,100 pounds is the minimum weight for a heavy load. This lift is, therefore, not a heavy load.
In addition to the above, a field inspection was performed and field measurements were taken of the monorail, the valve, and the minimum flow valve switch. It was determined through field inspection and measurements that there is enough clearance between the valve and plug and between the minimum flow valve switch and the plug.
Because of this clearance and because SQN only uses slings that meet the requirements of American National Standards Institute B30.9, lifting this concrete plug in the vicinity of the valve and minimum flow valve switch is acceptable; and there is no need for a trolley stop on this monorail.
Therefore, the staff agrees that the work associated with this commitment is not required.
2.2 Item 5 (Reference 4.1) "4-Ton Monorail Chain Hoist With Geared Trolley" Comitment TVA originally comitted to initiate a DCR to add trolley stops to the monorail, located in the auxiliary building on elevat'on 690 ft., to provide a safe load path.
Revised Response TVA provided the following information on this commitment for a safe load path, The work associated with this comitment pertains to the monorail over component cooling pumps IB-B and 28-B. The original comitment was based on the possibility that pump 1B-8 could be lifted over pump 28-B (or vice versa);
and, if the lifted pump was dropped, loss of component cooling system (CCS) inventory could occur. This scenario in turn could adversely affect the unit's ability to achieve and maintain a safe shutdown condition. A trolley stop was to be provided to ensure that one pump was not lifted over another.
Adding a trolley stop would prohibit lifting CCS pumps 18-B or 28-B over each other but would not keep the CCS pump motor from being lifted over the pump, causing the same concern. Installing a trolley stop would also interfere with setting down the pump or motor in the setdown area.
The addition of a trolley stop is not required because damaging CCS pumps 1B-B or28-B(and/orassociatedpiping)wouldonlycausealossofA-traininventory (these pumps are run in the A-train piping). Loss of A-train inventory because of either a dropped CCS pump or motor would not affect the B train of the CCS because the B-train inventory is separated from the A-train inventory, and shutdown could be achieved using the B train. This loss is bounded by the worst-case single failure.
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{
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p; s Worst-case flooding as a result of dropping a pump or pump motor is a total' loss of the A-train inventory that is bounded by the flood postulated in the moderate energy line break study.
.Therefore, TVA has concluded and the staff agrees that the work associated with this comitment is not required.
2.3 Item 6 (Reference 4.1? "3-Ton Capacity Jib Crane With 3-Ton Capacity-Wire Rope Electric Hod St and Chain Driven Trolley" Connitment TVA originally committed to revise Sequoyah Standard Practice SQM56 (curreritly Maintenance Instruction [MI] 6.22) to include the 3-ton jib crane in the reactor building on the list of heavy load handling equipment for miscellaneous lifts greater than 2,000 pounds.
Revised Response.
Based upon a review of TVA drawings (i.e., equipment drawings, mechanical
. instrumentation and control drawings, and mechanical piping drawings), TVA determined that the 3-ton-capacity jib crane does not need to be added to MI-6.22.
As a result of TVA's review, sample lines and control air lines were determined to be the only potential targets for a heavy load droy by this crane. However, TVA determined that there is sufficient physical separation from the load path to preclude this occurrence.
Therefore, TVA has concluded.and the staff agrees that the work associated with this comitment is not required.
3.0 CONCLUSION
For the. reasons stated above, the licensee's request for the withdrawal of their commitments is found to be' reasonable and acceptable.
4.0 REFERENCE
- 1. L.M. Mills's (TVA) letter to E. Adensam (NRC) dated March 1, 1982.
Principal Contibutor: S. B. Kim Dated:
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