ML20111A953

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

ML20111A953
Person / Time
Site:	Monticello
Issue date:	05/08/1996
From:	Hill W NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-96-002, IEB-96-2, NUDOCS 9605140102
Download: ML20111A953 (9)

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Northem States Power Company l Monticello Nuclear Generating nant 2807 West Hwy 75 Monticello. Minnesota 55362-9637 May 8,1996 Report Required by NRC Bulletin 96-02 )

i U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 l l

l' Response To NRC Bulletin 96-02 Movement Of Heavy Loads Over Spent Fuel, Over Fuelin the Reactor Core. Or Over Safety-Related Eauipment Following a review of the referenced Bulletin, we have concluded that Monticello is meeting the I licensing basis for movement of heavy loads during power operations. Attachment A contains our response to Bulletin 96-02; Movement Of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, Or Over Safety-Related Equipment; dated April 11,1996.

This letter contains r mw NRC commitments.

Pleese contact Torr ' rNer at (612) 295-1014 if you require further information.

/hfbter f'I William J Hill Plant Manager Monticello Nuclear Generating Plant c: Regional Administrator-lli NRC Sr Resident inspector, NRC NRR Project Manager, NRC State of Minnesota, Attn: Kris Sanda Attachments:

Affidavit of William J Hill A - Response to NRC Bulletin 96-02

._ I 9605140102 960500 PDR ADOCK 05000263 G PDR l 0

i UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 2

Response To NRC Bulletin 96-02 Movement Of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core. Or Over Safety-Related Eauipment Northern States Power Company, a Minnesota corporation, hereby provides the required 30 ,

day response to NRC Bulletin 96-02, " Movement Of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, Or Over Safety-Related Equipment." This letter contains no restricted or other defense information.

NORTHERN STATES POWER COMPANY By 8dem h //

William J HilV Plant Manager Monticello Nuclear Generating Plant On this day of b I 99 G2 before me a notary public in and for said County, personally appear 6d William J Hill, Plant Manager, Monticello Nuclear Generating Plant, and being first duly swom acknowledged that he is authorized to execute this document on behalf of Northem States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.

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Attachment A

- Page 1 of 7 i

Response To NRC Bulletin 96-02 Movement Of Heavy Loads Over Spent Fuel,. Over Fuel In ine Reactor Core. Or Over Safety-Related Eauioment

References:

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! ' 1) Letter dated July 7,1982, from Cavid Musoif to the Director of NRR titled:" Control of

! Heavy Loads (Revised Six Month Submittal)"

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2) Letter dated January 12,1982, from L 0 Mayer to the Director of NRR titled: " Control of j Heavy Loads (Nine Month Submittal)" ,

3) Letter dated December 22,1980, from the Darrell Eisenhut, Director of Licensing, NRR, to All Licensees of Operating Plants, titled:

• Control of Heavy Loads'

4) Letter dated March 19,1984, from Domenic B. Vassallo, NRC, to D. M. Musolf, titled 2 - " Control of Heavy Loads (Phase 1)"

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{ Request 1:

Address the licensee's review ofits plans and capabilities to handle heavy loads while the reactor

[ is at power (in all modes other than cold shutdown, refueling, and defueled) in accordance with j existing regulatory guidelines. The report should also indicate whether the activities are within i the licensing basis and should include, if necessary, a schedule for submission of a license amendment request. Additionally, the report shouldIndicate whether changes to Technical SpeciRcations willbe required.

Response to Request 1:

! Overhead Handlina Systems .

Monticello has two overhead handling systems from which a heavy load drop may result in damage to plant systems required for safe shutdown or decay heat i removal. These overhead handling systems are:

Overhead Handling; '

- Capacity (Tons)e ,

(Single Failure Proofi '

i System' Main Hookt 1 Auxiliary Hook - ' Y ' K Crane?Y " -

] Reactor Building Crane: 85 2.5' Yes Turbine Building Cranei 125 25 No ,

2

The Auxiliary Hook is designed to carry up to 5 tons. If it is used to carry heavy loads over spent fuel or safety related equipment, the capacity is reduced to 2.5 tons to provide a safety factor of 10.

Attachment A

• Page 2 of 7 All other overhead handling devices not included in the above list are provided in Figure 1. These either were excluded in accordance with our response to Generic Letter 81-07 (See Reference 1) or have been excluded subsequently using similar justifications.

Plans to Handle Heavy Loads While the Reactor is at Power All heavy load lifts over spent fuel and safe shutdown equipment are administratively controlled.

There are no administrative prohibitions on the Reactor Building Crane heavy load lifts at power, since the Reactor Building Crane has satisfied the " single failure proof" criteria'. Some of the loads that could be lifted at power are:

Cask' Weight (Ibs)'

IF-300 161,000 CNS 8-120B 74,000 CNS 3-55 70,000 CNS 8-120A 70,000 NUPAC 10-142 68,000 FSV-1 47,600 CNS 1-13G 34,000 CNS 1-13C 26,000 in the turbine building, the areas above safe shutdown equipment are marked with a pattern painted' on the turbine operating floor. Administrative restrictions on lifting heavy loads in this area limit the loads to less than 100,000 lbs and restrict the height to less than 6" above the floor during power operations.

Are Activities Planned Within the Licensina Basis?

All activities planned are within the Monticello licensing basis. The pertinent referenced licensing documents are referenc3d in the Monticello Updated Safety Analysis Report, Section 12.2.5.

The licensing basis of movement of heavy loads above safe shutdown equipment in the Turbine Building should be clarified. The following bracketed statement in the Technical Evaluation Report, prepared by Franklin Research 2

Technical Specification 3.7.C.2.d requires secondary containment when a fuel cask is being moved within the Reactor Building. '

8 Refered to as " crosshatched"in previous submittals.

l Attachment A f Page 3 of 7 Institute, containing the evaluation of safe load paths, is not considered part of f i the Monticello licensing basis (the brackets have been added): l Exclusion areas which have been developed in the tuttiine building are acceptable on  ;

j the basis that they are well defined, well marked, and normally exclude movements of all }

heavy loads. The licensee should ensure, however, that adequafie instructions and j wamings are included in formal administrative et load handling procedures to prevent j i- non-approved movements into this exclusion area. In addition, the instance noted (1984 maintenance outage) by the Licensee in which movements into this area will occur j l-appears to be acceptable on the basis that the deviation has been reviewed and

f approved by the Operations Committee and a formal procedure has been prepared for r use. [However, the Licensee should ensure that, following completion of the major  ;

maintenance, movements of heavy loads into the exclusion area are again prohibited  ;

]

and that the procedure is removed from use. Future movements of heavy loads into the j

turbine building exclusion area should be identified and approved by the Operations l

Committee on a case-by-case basis so that the movements are clearly identified and  ;

individually approved).

i The conclusion and recommendation section states: " implementation of safe load paths and exclusion areas at the Monticello Nuclear Generating Plant is consistent with Guideline 1 of NUREG-0612." No recommendations were  ;

made. l

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Movement of heavy loads over safe-shutdown equipment is permitted per the  ;

NRC guidance on responding to the Control of Heavy Loads issue Enclosure 4

of Reference 3, which states:  ;

i Where safe-shutdown equipment has a ceiling or wall separating it from an overhead handling system, provide an evaluation to demonstrate that postulated load drops do not - ,

l l penetrate the ceiling or cause secondary missiles that could prevent a safe-shutdown system from performing its safety function.

! Monticello had an analysis performed to demonstrate that load drops up to  ;

i 100,000 lb from 6" on the Turbine Operating floor would not generate secondary l missiles that could prevent a safe-shutdown system from performing its safety

function. This analysis is the current at power licensing basis.

The NRC Safety Evaluation Report (Reference 4) stated: "The staff has l _ reviewed the Technical Evaluation Report and concurs with its findings that the (

guidelines in NUREG-0612, Sections 5.1.1 and 5.3 have been satisfied. We therefore conclude that Phase I for Monticello is acceptable." Typically, NRC

[ Safety Evaluation Reports will identify any additional actions needed to be taken .

by the licensee. None were identified in this Safety Evaluation Report. The  !

. - action mentioned in the Technical Evaluation Report was not a commitment  !

- made by NSP nor was it identified in the NRC Safety Evaluation Report.

-Therefore, Monticello does not consider it part of the plant licensing basis.  ;

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' Attachment A i

Page 4 of 7 i- Generally, when Monticello identifies statements in Safety Evaluation Reports

that need clarification, this is communicated to the NRR Project Manager. In this case, the licensing engineer failed to communicate this clarification to the NRC.

This was an oversight. l

} The procedure referenced by the Technical Evaluation Report was not deleted

and is in use today. - it has been revised 5 times and each revision was reviewed by the Operations Committee. No loads in excess of 100,000 lbs have been

lifted over this area at power. In summary, all past activities and planned activities are within the Monticello licensing basis.

i ' Are Chances to the Technical Specifications Required?

No changes are needed to the Monticello Technical Specifications. I

- Request 2:

For licensees planning to pertbrm activities involving the handling of heavy loads over spent fuel,

fuelIn the reactor core, or safety-related equipment while the reactoris at power (in all modes

other than cold shutdown, refueling, and defueled) and that involve a potentialload drop accident that has not previously been evaluated in the FSAR, submit a license amendment request in advance (6-9 months) of the planned movement of the loads so as to afford the staff sut!!cient f time to perform an appropriate review.

i 1 Response to Request 2: l

. The handling of heavy loads by the Turbine and Reactor Building Crane has been <

! reviewed by the NRC Safety Evaluation Report (Reference 4).

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- 1 Request 3:

Forlicensees planning to move dry storage casks over spent fuel, fuelin the reactor core, or 1 sakty-related equipment while the reactoris at power (in all modes other than cold shutdown,

. refueling, and defueled) include in item 2 above, a statement of the capability of performing the actions necessary for sak shutdown in the presence ofradiological source term that may result

trom a breach of the dry storage cask, damage to the fuel, and damage to safety-related  !

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equipment as a result of a load drop inside the facility. j

Response to Request 3

! Monticello is not licensed to handle dry storage casks.

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Attachment A

• Page 5 of 7 Request 4:

Forlicensees planning to pertban activities involvlng the handling of heavy loads over spent fuel, fuelin the reactor core, or safety-related equipment while the reactor Is at power (in all modes

other than cold shutdown, refueling, and defueled), determine whether changes to Technical

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Specifications will be required in order to allow the handling of heavy loads (e.g., the dry storage ,

, canister shleid plug) over fuel assemblies In the spent fuel pool and submit the appropriate inIbrmation in advance (6-9 months) of the planned movement of the loads for NRC review and

approval.

4 i Response to Request 4:

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No changes are needed to the Monticello Technical Specifications.

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• Page 6 of 7 l l

Figure 1: Handling Devices Not Requiring Heavy Loads Movement Procedures as of May 1996 a

Handling Device Capacity (LBs)

Reactor Building Reactor Recirc Pumps Monorail Motor Hoist 32,000 Radwaste Storage Bridge Crane 20,000 New Shipping Building Crane 20,000 Radwaste Conveyor Load-Out Monorail 12,000 I

RWCU Filter Shield Block Monorail 10,000 HPCI Turbine Monorail 8,000 Radwaste Building Monorail 6,000 Radweste Building Sump Monorail 6,000 Rx Building Closed Clg Wtr Heat Exchanger Lifting Lugs 6,000 MSIV Area Monorail 6,000 HPCI Pump Monorail 6,000 Radwaste Centrifuge Hoist A 4,000 Radwaste Centrifuge Holst B 4,000 Drywell Equipment Hatch Monorail and Lifting Device 3,000 Reactor Building Elevator 2,100 Radwaste Devices Entrance Monorail 2,000 H-26-Holst Rx Bldo 896' Tank Room Jib Crane 2,000

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Refueling Facilit!es Motor Drive Jib Crane A 1,500 Refueling Facilities Motor Drive Jib Crane B 1,500 Reactor Vessel Service Platform 1,500 Torus Monorail at AZ 300* 1,500 Lifting Lugs in Torus Room over Ring Header Snubbers (9) 1,500 Torus Ro_o,n, jing Lug above AO-2381 1,500 Torus Rt c ,j, k 1 Lug above AO-2377 (2) 1,500 Torus Rourtj i,9 Lug above AO-2378 (3) 1,500 Toruc Room L. ..no Lug above AO-2380 (3) 1,500 HPCI Jib Crane 2000 LB Lifting Lugs above Drywell Hatch (4) 1,500 CRD Rebuild Area Monorail 1,000

$ Low Level Contamination Work Area Monorail 1,000 t MSIV Area Lifting Lug 1,000 Radwaste Capping Station Monorail 1,000 Rx Refueling Platform Handling Device 1,000 Radwaste Barrel Compactor Monorail 1,000 1

Jib Crane over RBCCW Pump P-6A 1,000 Jib Crane over RBCCW Pump P-6B 1,000 Jib Crane over Snubber Rebuild Shop 1,000 962 Tool Storage Jib Crane 1,000 ,

Torus Room Lifting Lug above MO-2110 800 l Torus Room Lifting Lug above MO-3502 500 Refueling Facilities Channel Handling Jib Boom 50 Channel Handling Overhead Rigging 50  !

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Attachment A a Page 7 of 7 Handling Device Capacity (LBs)

Diesel Generator Building Diesel Generator A Monorail, A and B Lifting Lugs 470 Diesel Generator B Monorail, A and B Lifting Lugs 470 Turbine Building "A" Turbine Floor Portable A-Frame and Monorail 10,000 "B" Turbine Floor Portable A-Frame and Monorail 10,000 Hot Machine Shop Monorail 4,000 Rx Feedwater Pump A Monorail 2,000 Rx Feedwater Pump B Monorail 2,000 Hot Machine Shop Jib Crane and Lifting Lug 2,000 C Turbine Building Portable A Frame Monorail C 1,500 Condensate Demin Holding Pump A Hatch Monorail 1,500 Condensate Demin Holding Pump B Hatch Monorail 1,500 Condensate Demin Holding Pump C Hatch Monorail 1,500 Condensate Demin Holding Pump D Hatch Monorail 1,500 Condensate Demin Holding Pump E Hatch Monorail 1,500 Turbine Floor Lifting Beam (Over Tool Crib and Lathe) 1,500 No.11 Air Compressor Jib Crane 1,500 No.12 Air Compressor Jib Crane 1,500 No.13 Air Compressor Jib Crane 1,500 No.14 Air Compressor Jib Crane 1,500 Electric Breakers Bridge Holst Room A 1,000 Electric Breakers Bridge Hoist Room B 1,000 Jib Crane (above F.W. haaters 15A &158) 1,000 Heating Boiler Room Monorail 500 Intake Structure Screen House Bridge Crane 10,000 Trash Basket Jib Crane 4000 OffGas Storage Building Off-Gas Storage Building Jib Crane 15,000 Off-Gas Stack Monorail 6,000 Off-Gas Storago Building Monorails 1000 l

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