ML20079Q180

Forwards Response to Open Item on Safe Load Paths Contained in NRC 820923 Technical Evaluation Rept of Util 820201 Submittal Re Control of Heavy Loads (NUREG-0612)

ML20079Q180
Person / Time
Site:	Davis Besse
Issue date:	05/06/1983
From:	Crouse R TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 946, TAC-10993, NUDOCS 8305110385
Download: ML20079Q180 (11)

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TOLEDO

%sm EDISON Row.o P Caou t y e m,. 4 fh4*

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ed I 9, g L J " M I Docket No. 50-346 License No. NPF-3 Serial No. 946 May 6, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Stolz:

This is in response to your letter dated September 23, 1982 (Log No.

1094) concerning " Control of Heavy Loads at Nuc1 car Power Plants (NUREG-0612) Technical Evaluation Report. The attachment contains our response to the open item on Safe Load Paths for the Davis-Besse Nuclear Power Station Unit No. 1.

Very truly yours, n o ,-

,jn l L %s~~ x- 9 y%

RPC: CAB:lah attachment cc: DB-1 NRC Resident Inspector J

8305110385 830506 PDR ADOCK 05000346 P PDR THE TOLEDO EDISON COMPANY EO SON PLAZA 300 MADISON AVENUE TOLEDO. OH10 43652

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l RESPONSE TO NRC/FRC QUESTlONS ON THE REVIEW OF TOLEDO EDISON"S FEBRUARY 1,1982 6-MONTH SUBMITTAL ON NUREG-06121SSUES SAFE LOAD PATHS I

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QUESTION: " Davis-Besse Unit I partially complies with Guideline 1. Load paths have been designated for those loads in Handling Class 3B; however, the Licensee should forward drawings that identify and define the extent of these load paths.

To fully comply with this guideline, the remaining actions should be taken by the Licensee:

1. For remaining Class I, 2, and 3A loads, develop one or more general-purpose or preferred load paths which allow movement of loads in areas of concern.

2. Incorporate load paths into general arrangement drawings and provide suitable visual aids to the operators when transporting loads."

RESPONSE: Our submittal of February 1,1982 supplied information related to safe load paths for heavy load handling operations at Davis Besse. This submittal identified a number of handling classes (classes I, 2, 3A,3B and 4). The purpose of the handling classes was to help identify on appropriate level of administrative controls for each load handling situation based on the potential consequences of postulated load drops. In accordance with the NRC's two phased approach to the heavy load issue, this initial effort was undertaken prior to any specific evaluation of potential load drop consequences (Phase 2). Franklin Research Center's (FRC) evaluation of our submittal relative to safe load paths resulted in several outstanding items involving the need for more specific " safe load paths" for certain classes of loads. (See pages 12,13 and 14 of draft TER-C5257-530.)

We have been considering FRC's conclusions and recommendations including the desirability of more specific safe load paths. At the some time, we have I

essentially completed the second phase of our heavy loads review, i.e., the evaluation of load drop consequences. A preliminary report to NRC is in the final stages of preparation.

The results of the load drop consequence evaluations have caused us to reconsider our initial conclusions regarding safe load paths and other administra-tive controls for heavy load handling operations. Based on these evaluations, we have redefined the set of administrative controls for heavy load handling operations to specifically address the heavy load handling situations of potential safety significance and to remove restrictions on load handling situations with no potential safety significance. The result of these efforts was:

(1) Specific " safe load paths" for the handling systems identi-fied in our February 1,1982 submittal were found to be for major loads associated with reactor necessary disassembly. only l /This is based on system redundancy and diversity considerations and structural evaluation of the protection offered by intermediate structures, e.g., slabs and other structural elements.

(2) The restricted crea identified as Region A in the contain-ment in Figure 2 of our February 1,1982 submittal re-mains in effect. Additional administrative controls will be implemented in procedures to better control the move-ment of loads that must be moved into and out of this restricted area.

3) Additional administrative controls will be implemented in procedures to assure that safety system redundancy is available when lif ts are made over certain areas and to assure that the expected degree of protection is provided by certain slabs and other structural elements (limits on heights of carry in certain areas).

l/ Note that load paths are defined by polar crane match marks for the Reactor Vessel Closure Head and the Plenum Assembly. Use of these match marks is currently required by procedures.

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It is our conclusion, that with these revisions and additions to our current set of administrative controls for heavy loads, the potential safety issues have been specifically addressed and any additional controls, e.g., detailed safe load paths, would only serve to unnecessarily restrict the flexibility of our operations and maintenance staffs to safely and efficiently perform their functions.

A revised listing of heavy loads for each of the handling systems of interest with references to procedures where the appropriate administrative controls have or will be implemented is provided in Tables I through 4.

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TABLEI POLAR CRANE HEAVY LOADSI APPROX. APPLICABLE WElGHT OPERATING LIFTING LOAD (POUNDS) PROCEDURES EQUIPMENT

l. Reactor Plenum Assembly 2 119,000 SP i l04.465 plenum Assembly SP l505.01 Lifting Rig 2

2. Reactor Vessel Head 3 330,000 SP i l04.46 Reactor Vessel SP l504.016 Head Lif ting Rig

3. Internals Indexing Fixture 4 31,100 SP 1104.46 Plenum Assembly SP l505.01 Lifting Rig 2

4. Plenum Assembly Lifting Rig 18,500 SP I 104.46 N/A SP l505.01 7

5. Automatic Reactor 32,000 SP I 104.46 Slings and Shackles Inspection System (ARIS)

6. I-Beam D-Ring Grating 12,000 SPI 104.46 Wire Rope Slings Supports and Shackles

7. Steam Generator Removable 14,100 SPI 104.46 Wire Rope Slings Supports Supports and Shackles

8. Reactor Missile Shields (6) 94,500 ea. M-73 Reactor Missile SPI 104.46 Shield Lif ting Harness

9. Polar Crane Load Block iI,200 SP I 104.46 N/A

10. Steel Working Platform 2,700 SP I 104.46 Wire Rope Stings and Shackles

11. 20" Steam Generator Snubbers 7,000 SP i l04.46 Wire Rope Slings and Shackles

12. Irradiated Specimen Cask 6,000 SP I 104.46 Wire Rope Slings and Shackles

TABLEI (continued)

APPROX. APPLICABLE WEIGHT OPERATING LIFTING LOAD (POUNDS) PROCEDURES EQUIPMENT

13. Letdown Coolers 5,000 SPI 104.46 Wire Rope Slings and Shackles 14 Equipment Hatch Covers (Region 2) SP I 104.46 Wire Rope Slings o 603' el. - 4 covers for I hatch 10,000 ea.

o 585' el. - 2 covers for a hatch 32,000 ea.

15. Core Flooding Tank Hatch 8,000 ea. SP I 104.46 Wire Rope Slings Covers for each of 2 hatches and Shackles (Regions 2 and 9)

16. In-Core Instrument Tank 6,800 eo. SP I 104.46 Wire Rope Slings Access Hatch Covers at ar'd Shackles 603' el. (Region 8)

17. Motor Removal Hatches at 5,000 ea. SP I 104.46 Wire Rope Slings 603' el. - I cover for each and Shackles of 2 hatches (Region 2)

18. Plenum Assembly Stand 6,000 SP l 104.46 Wire Rope Slings and Shackles

19. Core Support Barrel Stand 6,500 SP I 104.46 Wire Rope Slings and Shackles

20. Reactor Vessel Head 12,000 SPI 104.46 N/A Lif ting Rig SP l504.01

21. Reactor Coolant Pump (RCP) 4,000 SP I 104.46 Wire Rope Slings Rotating Element and Shackles

22. RCP Motor 102,000 SPI 104.46 Wire Rope Slings and Shackles

23. Reactor Coolant Pump 84,000 SP I 104.46 Wire Rope Slings and Shackles

24. Core Support Assembly 224,000 SP I 104.46 Core Support SP l505.01 Assembly

25. Reactor Cavity Seal Ring 3,000 SP I 104.46 Wire Rope Slings and Shackles

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l TABLEI (continued)

APPROX. APPLICABLE i WEIGHT OPERATING LIFTING l LOAD (POUNDS) PROCEDURES EQUIPMENT

26. Refueling Canal Walkways (2) 2,700 SPI 104.46 Wire Rope Slings and Shackles i

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1. For reference, a heavy load is defined as the weight of a fuel assembly plus its handling tool; 2,430 lbs. .

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2. The total weight of the Plenum Assembly lift includes: the Plenum Assembly, and the Plenum Assembly Lifting Rig. This lif tir,g rig includes

> the following components: Head and internals Handling Fixture; Head and i l internals Handling Extension; and the Internals Handling Adapter, Pendants, i and Spreader Ring.

3. The total weight of the Reactor Vessel head lif t includes: the head; the service structure; studs, nuts, and washers; and the Reactor Vessel Head Lif ting Rig. This lifting rig includes the following components: Head and Internals Handling Fixture, Head and internals Handling Extension, two turnbuckle pendants, and three head lif ting cables.

4. The total weight of the Internals Indexing Fixture includes: the Indexing Fixture and the Plenum Assembly Lif ting Rig, i

5. SP l 104.46, " Polar Crane System Procedure."

i 6. SP 1505.01, " Reactor Vessel Closure Head Removal and Replacement."

7. SP 1505.01, " Reactor Internals Removal and Replacement."

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.. __ . . . _ ._. _ _ ... _ _ _ . _ _ _ _ _ _ . ___ _ = _ . _ _ _ . . _ _ _

TABLE 2 COMPONENT COOLING WATER PUMP MONORAll (3) HEAVY LOADS APPROX. APPLICABLE WEIGHT OPERATING LIFTING LOAD (POUNDS) PROCEDURES EQUIPMENT Component Cooling Water 5,400 SP 1104.131/ Slings and Pumps Shackles Component Cooling Water 4,800 SP 1104.13 Slings and Pump Motors Shackles I. SP 1104.13, " Component Cooling Water Pumps Monorail System Procedure."

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TABLE 3 SPENT FUEL CASK CRANEl HEAVY LOADS APPROX. APPLICABLE WEIGHT OPERATING LIFTING LOAD (POUNDS) PROCEDURES EQUIPMENT Pool Divider Gates 8,000 SP I 104.502 Wire Rope M-543 Slings and Shackles

1. This crane is used to handle loads in the Equipment and Fuel Handling Area and for loads around the spent fuel pool. It will eventually be used to handle spent fuel casks. Loads lif ted in the Equipment and Fuel Handling Area are not carried near the spent fuel pool and, therefore, are not listed in this table.

2. SP 1104.50," Spent Fuel Cask Crane Operating Procedure."

3. Maintenance Instruction M-54, Removal / Replacement of Gate Between the Spent Fuel, New Fuel Storage / Transfer Pools.

TABLE 4 INTAKE GANTRY CRANE HEAVY LOADSI APPROX. APPLICABLE WEIGHT OPERATING LIFTING LOAD (POUNDS) PROCEDURES EQUIPMENT

l. Service Water Pump 7,800 SPI 104.53 1 All Intake Gantry Crane heavy loads are lifted with wire rope slings and shackles

2. Service Water Pump Motor 8,600 SP I 104.53

3. Cire Water Makeup Pump 5,700 SP l 104.53

4. Makeup Pump Motor 3,500 SP I 104.53

5. Roof Top Hatch Covers 2,800 SP l 104.53

6. Dilution Pump 9,500 SP l 104.53

7. Dilution Pump Motor 3,000 SP I 104.53

8. Diesel Fire Pump 5,200 SP I 104.53

9. Diese! Fire Pump Motor 3,500 SP I 104.53

10. Screen Wash Pump 3,560 SP 1104.53 II. Screen Wash Pump Motor 1,300 SP I 104.53

1. SPI 104.53, " Intake Gantry Crane System Procedure."