ML19344A903

Forwards Response to Requesting Info Re Control of Heavy Loads Near Spent Fuel

ML19344A903
Person / Time
Site:	Point Beach
Issue date:	07/28/1978
From:	Burstein S WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, Stello V Office of Nuclear Reactor Regulation
Shared Package
ML19344A904	List: ML19344A903
References
REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR 780828, TAC-07727, TAC-08074, TAC-7727, TAC-8074, NUDOCS 8008220576
Download: ML19344A903 (6)

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l Wisconsin Electnc ecw:a coupsur 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201 July 28, 1978 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY C0144ISSION Washington, D. C.

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Attention: Mr. Victor Stello, Director Division of Operating Reactors Gentlemen:

DOCKET NOS. 50-266 AND 50-301 MOVEMENT OF HEAVY LOADS OVER SPENT FUEL POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 On May 30, 1978, we received your letter dated May 17,1978, which forwarded an information request concerning the control of heavy loads near spent fuel.

By letter dated June 12, 1978, you acknowledged an adninistrative error concerning this letter and provided us with a corrected copy of the May 17, 1978 letter. We have providea herewith our responses to your information request.

Since most of this information has been previously provided to the NRC, we have specified references to where the information may be found.

Should you have any additional questions regarding your review of this naterial, please contact us.

Very truly yours, 4M5 Sol Burstein Exec tive Vice President Attachment 9 c m o 5 7 6.

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Question 1 Provide a diagram which illustrates the physical relation between the reactor core, the fuel transfer canal, the spent fuel storage pool and the set down, receiving or storage areas for any heavy loads moved on the refueling floor.

RESPONSE

Your attention is invited to diagrams available in the Point Beach Nuclear Plant Final Facility Description and Safety Analysis Report (FFDSAR) Chapter 1, in Appendix F and to our letter to Mr. George Lear, dated May 15, 1975.

Question 2 Provide a list of all objects that are required to be moved over the reactor core (during refueling), or the spent fuel storage pool.

For each object listed, provide its approximate weight and size, a diagram of the movement path utilized (including carrying height) and th7 frequency of movement.

RESPONSE

A list of heavy objects that are required to be moved over the spent fuel storage pool was identified in our letter to Mr. Rusche dated October 2,1975.

From that list one can delete the spent resin cask and liner, since we have completed installation of a waste solidification system which precludes the necessity of moving the spent resin cask and liner across the spent fuel pool.

Question 3 What are the dimensions and weights of the spent fuel casks that are or will be used at your facility?

RESPONSE

The dimensions and weight of the speat fuel shipping casks that have been utilized at Point Beach are provided in Appendix F of the FFDSAR.

_- _____ Question 4 Identify any heavy lor.d or cask drop analyses performed to date for your facility.

Provide a copy of all such analyses not previously submitted to the NRC staff.

RESPONSE

Cask drop analysis information has been provided to the NRC with our letter to Mr. O' Leary dated May 21, 1974, which forwarded FFDSAR Amendment 15, and those letters referenced in items 1 and 2 above.

Much of this information was consolidated in Appendix F to the FFDSAR as amended by Amendment 23 dated October 14, 1977.

Question 5 Identify any heavy loads that are carried over equipment required for the safe shutdown of a plant that is operating at the tima the load is moved.

Identify what equipment could be affected in the event of a heavy load handling accident (piping, cabling, pumps, etc.) and discuss the feasibility of such an accident affecting this equipment.

Describe the basis for your conclusions.

RESPONSE

A list of equipment under the spent fuel shipping cask movement path is provided and discuss in Appendix F to the FFDSAR.

Question 6 If heavy loads are required to be carried over the spent fuel storage pool or fuel transfer canal at your facility, discuss the feasibility of a handling accident which could result in water leakage severe enough to uncover the spent fuel.

l Describe the basis for your conclusions.

RESPONSE

This information is provided and discuss in Appendix F to the FFDSAR.

Questiq7j7 Descr's any design features of your facility which affect the potential for a heavy load hardling accident involving spent fuel, e.g., utilization of a single failure-proof crane.

RESPONSE

This information is provided in our May 15, 1975 letter and Appendix F to the FFDSAR.

We would also direct your attention to our March 21, 1978 letter to Mr. Edson G.

Case which discusses a proposal to single failure-proof the auxiliary building crane and our July 19, 1978 letter to Mr. Denton which responded to NRC questions on this design.

Question 8 Provide copies of all procedures currently in effect at your facility for the movement of heavy loads over the reactor core during refueling, the spent fuel storage pool, or equipment required for the safe shutdown of a plant that is operating at the time the move occurs.

RESPONSE

The applicable portions of our auxiliary building crane loading handling procedures hsve been included in Appendix F of the FFDSAR.

Question 9 Discuss the degree to which your facility complies with the eight (8) regulatory positions delineated in Regulatory Guide 1.13 (Revision 1 December,1975) regarding Spent Fuel Storage Facility Design Basis.

RESPONSE

This item requests that licensee discuss the degree to which h.he facility complies with the eight regulatory positions delineated in Regulatory Guide 1.13, Revision 1.

A short discussion on each position follows:

1)

The concrete structural portions of the primary auxiliary building, within which the spent fuel storage pool is located, is designed to Category 1 seismic requirements. The metal walls and roof structure of the building were designed to maintain their structural integrity without collapse in the event of a seismic occurence.

l 2)

As discussed in the response to question 9.3 in the FFDSAR, the walls and base of the spent fuel pool are designed to withstand tornado generated missiles.

Calculations were provided in topical report B-TOP-3 which demon-strated that tornado generated winds would not remove any critical amounts of water from the spent fuel pool.

3)

Auxiliary building crane travel interlocks to prevent movement of heavy loads over or in proximity to the south spent fuel pool have been provided as discussed in Appendix F and the plant Technical Specifications.

j 4)

The spent fuel pool at Point Beach Nuclear Plant is enclosed by a controlled leakage building with an appropriate ventilation cnc filtration systs. An analysis of potential off-site doses using the assumptions given in Regulatory Guide 1.25 was provided with our letter to Mr. Rusche dated March 14, 1977.

5)

The design of the Point Beach facility does not presently incorporate any of the provisions suggested in this position. As discussed in the response j

to item 7 above, licensee has applied for a license amendment which includes i

a modification to the auxiliary building crane to provide a redundant lifting system.

6)

The design of the Point Beach Nuclear Plant spent fuel pool precludes the loss of coolant that would uncover the fuel due to a failure or maloperation of drains and permanently connected mechanical or hydraulic systems.

7)

Suitable monitoring instrumentation for both pool water level and local radia-tion levels are provided. The spent fuel pool filtration system is operated manually.

8)

A seismic Category 1 backup system is provided to add coolant to the spent fuel pool.

Several additional makeup systems exist which could provide

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__ _ _ backup to the spent fuel pool. The pool cooling system and backup water supplies are discussed in Section 9.3 and Appendix F of the FFDSAR.

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h REGilLATORY INF00WATION DISTRIBUTION SYSTEV (9105)

ACCESSION tl'iR 7702000340 DOC.DATE: 79/02/07 NOTA RI 7.ED: YES 00CKET

• FACIL 50-265 Polot Reach Nuclear Plant. Unit 1.

niscnosin Electric 05000266 50-301 Poin'. Reach Nuc lear Plant. Uni t 2.

Wisconsin Electric 05000301 UTH. N A ME AUidOR AFFILIATION BU9 STEIN.S.

disconsin Electric Power Cn.

7ECI P. N A'!E RECIPIENT AFPII.! ATION DENTON,H.R.

Office of Nuclear 9eactor 9eculation SC4 HENC Ei?, 4.

Oper'ating Reactors Branch i sui)ECT: Su5mits mod to Tech Soec chaqqe request 54 re addl restri ctions on move-ent of heavv loads i coeration of auxilierv hido crane ovar 9 pent f uel storad in fuel onol.

DISTRIPUTI')N CODE: A033S COPIES PECEIVED LTR.3t ENCL 3 SIZE TITLE: Control of Heavy Loads Naar Soent Foal dOTFS

'T +2 3_ cM S of kt-L MVfL.

RECIPIENT COPIES RECIPIENT COPIES ID CODE / NAVE LTTR ENCL ID CODE /NAME LTER FNCL 7

7 ACTION:

05 BC o g gg INTRNAL: 01 REG FILE I

I 02 NRC PDP 1

1

12. I&E 2

2 14 HANAUER I

i 15 CORE PERF BR I

I 16 AD SYS/PP()J l

1 17 ENGR BR I

1 18 REAC SFTY R9 1

1 19 PLANT SYS BR I

I 20 FEB 1

1 21 "~ ~ ~ r ?

'S I

I 22 BRINKHAN I

I 23 bGHRORS. DD I

I 24 FERRELL.C.

I I

25 WOHL.A.

I I

26 CLEMENSON F.

1 I

27 LANfZ,E.

I I

28 7.'IDA NS. J.

I I

29 ACRS 16 16 EXTERNAL: 03 LPDR 1

1 04 NSIC 1

I t

TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 44