ML20116A929

Submits Corrected Response to NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core or Over Safety-Related Equipment

ML20116A929
Person / Time
Site:	San Onofre
Issue date:	07/23/1996
From:	Marsh W SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-002, IEB-96-2, NUDOCS 9607290033
Download: ML20116A929 (5)

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Southem Califomia Edison Company P. O. BOX 128 SAN CLEMENTE, CALIFORNIA 92674-0128 wAuen c. uAnss MANAGER OF NUCLEAR REGULATORY arf AIRS July 23, 1996 va'ee"O~e (714)368-7501 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 Correction to the Response to NRC Bulletin 96-02, " Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or Over Safety Related Equipment" San Onofre Nuclear Generating Station Units 2 and 3

Reference:

Letter from W. C. Marsh (Edison) to the Document Control Desk (NRC); dated May 14, 1996,

Subject:

Docket Nos. 50-361 and 50-362 Response to NRC Bulletin 96-02, " Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or Over Safety Related Equipment," San Onofre Nuclear Generating Station, Units 2 and 3 This letter provides a correction to the referenced May 14, 1996, letter, the Southern California Edison (Edison) response to NRC Bulletin 96-02. The enclosed table has been revised to show that Item 6, the Component Cooling Water (CCW) hatch cover lift, was required to support emergent work concurrent with the preparation of the referenced May 14 letter. Two lifts of the CCW hatch cover, one to remove the hatch cover and the other to replace it, were performed on May 15, 1996, and May 17, 1996, respectively.

As indicated in the enclosed table, the CCW hatch cover lift was identified in previous Edison submittals, and war reviewed by the NRC.

If you have any questions in this rnatter, please call me.

Sincerely, 9607290033 960723 W0 PDR ADOCK 05000361 g G PDR t v

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Enclosure i' 3

i Docume'nt Control Desk cc: L. J. Callan, Regional Administrator, NRC Region IV J. C, Dyer, Director, Division of Reactor Projects, Region IV K. E. Perkins -Jr., Director, Walnut Creek Field Office, NRC Region IV J. A. Sloan, ~ NRC Senior Resident Inspector, San Onofre Units 2 & 3

• M. B. Fields, NRC Project Manager, San Onofre Units 2 and 3

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ENCLOSURE 1

' San Onofre Units 2 and 3 Heavy Loads During Modes 1 through 4 and Over or Near Spent Fuel or Safe Shutdown Equipment Weight or Plan to Lif t Design Included in within next Capacity Previous NRC 2 Heavy Loads by Crane (1) (tons) Submittals? years?")

1) Containment Polar Crane") 205/30/1 Yes CRDM Missile Shield Blocks") 88.5") Yes Yes

2) Cask-Handling Crane") 125/10 Yes Irradiated Fuel Shipping Cask") 125 Yes No Spend-Fuel Pool Gate") 2.2 Yes No

3) Turbine Gantry Crane 225/60/20 Yes-Salt Water Cooling Pump Motor") 3 Yes .Yes Misc. Loads")U') --

Yes Yes

4) New Fuel Handling Crane 5 Yes Spent-Fuel Pool Gate") 2.2 Yes No

5) AFW Pump Bridge Crane 5 Yes AFW Pump Motor (Elec.) 4.9 Yes No AFW Pump (Elec.) 3.3 Yes No AFW Pump (Turbine) 2.5 Yes No

6) CCW Pui.ip Monorail' 3 Yes CCW Pump Motor") 3 Yes No Hatch Cover") 2.1 Yes Yes

7) Safety Injection Pump Monorails 4 Yes HPSI Motor 2.9 Yes No LPSI Pump 3.8 Yes No LPSI Motor 2.8 Yes No Containment Spray Pump 3.8 Yes No Containment Spray Motor 2.8 Yes No Hatch Cover 2.9 'les No 8). Penetration Jib Hoists'l&2 6 Yes 480V Transformer Core 3.5 Yes"" Yes Tendon P1atform") 5 Yes Yes

. ENCLOSURE 1 Weight or Plan to Lift Design Included in within next Capacity Previous NRC 2 Heavy Loads by Crane (1) (tons) Submittais? years 7m

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9). TGC Side BoomW - 10 Yes-Tendon Platform 5 Yes Yes

10) .- Diesel Bldg. Bridge Crane 3 Yes'-

Diesel Generator Parts <3 See note 12 Yes

11) Charging. Pump Monorails 5 Yes Charging Pump & Components <5 See Note 12 Yes Notes: 1) Load Block / Hook weights are not included in the tabulation of load weights.

Load Blocks and hook weights are considered in performing load drop evaluations. Loads less than 1500 lbs., excluding the weight of hooks and load blocks, are considered routine lifts and do not receive special consideration as heavy loads.

2) This column identifies lifts currently being planned. The need to perfonn many of the lifts is contingent upon equipment performance and overhaul schedules. As such, those lifts that are indicated as 'No" may be performed if necessary per the current SONGS NUREG-0612 program.

3) The load block and hook (10 tons main /1.8 tons aux) with loads less than 1500 pounds may be moved during plant Modes 3 through 6.

4) Missile shield may be removed / installed during shutdown Modes 4, 5, and 6.

5) The Edison submittals and the NRC Safety Evaluation Report, the References of Enclosure 2, contain an incorrect weight of 22.5 tons for the missile shield.

The correct maximum weight of 88.5 tons from Calculation C-257-06.07 is shown.

6) Cask Crane is physically incapable of passing over the spent fuel pool.

However, emergency firewater tankers may be stored in the truck bay and are required to be removed or declared out of service while crane operations are made overhead.

7) The cask crane does not pass over spent fuel or safe shutdown equipment.

However, the cask may contain spent fuel assemolies. Hence, it is included in this sumary.

8) Ga'> removal / installation requires special rigging. The potential drop of a gatt on the spent fuel racks is analyzed.

9) Load is carried over an intervening structure protecting safety related or safe shutdown equipment.

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, ENCLOSURE 1

10) These loads are not specifically identified in the submittals. Miscellaneous loads less than 1500 lbs. are routine lifts and can be moved without restrictions. Loads greeter than 1500 lbs. must comply with safe load path requirements. Miscellaneous loads which are allowed to be carried over the saltwater pump building with lift height restrictions include, but are not limited to traveling screens & rakes, mobile cranes, manlifts, saltwater cooling pumps, screen wash pumps, circulating water pump bellows, and roof plugs.

In addition, 480V transformers are placed upon the roof of the auxiliary building with lift height restrictions. The lift avoids passing over the saltwater pump building and only traverses an area of the auxiliary building where no safe shutdown equipment is located directly below. The auxiliary building roof is also capable of withstanding a transformer drop.

11) The load path for this lift is over a single train of the component cooling water system. In Reference 4 of Enclosure 2, the June 30, 1982 submittal, Edison stated that transformer replacements will only occur during cold '

shutdown. A 10 CFR 50.59 safety evaluation has been prepared to allow this lift during plant operation using two independent hoists to meet the single failure protection criteria of NUREG-0612.

12) Crane is an exempt load handling system based on design redundancy. A load drop by this lifting device would not damage multiple trains of safety related / safe shutdown equipment. In addition, when lifts are made over safe shutdown equipment, that equipment is declared out of service.

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