ML19308D938

Forwards Response to NRC 780517 Request for Addl Info Re Movement of Heavy Loads Near Spent Fuel

ML19308D938
Person / Time
Site:	Crystal River
Issue date:	08/18/1978
From:	Stewart W FLORIDA POWER CORP.
To:	Stello V Office of Nuclear Reactor Regulation
References
NUDOCS 8003200687
Download: ML19308D938 (15)

Text

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< REGULATORY INFORMATION DISTRIBUTION GYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-302 REC: STELLO V ORG: STEWART W P DOCDATE: 08/18/78 NRC FL PWR DATE RCVD: 08/25/78 DOCTYPE: LETTER NOTARIZED: YEG COPIES RECEIVED -

SUDJECT: LTR 3 ENCL 40 RESPONSE TO NRC REQUEST OF 05/17/70. FORWARDING ADDL INFO CONCERNING MOVEMEtJT OF llEAVY LOADS NEAR SPENT FUEL AT SUBJECT FACILITY. W/ATT REV 2

" SURVEILLANCE PROCEDURE GP-434 FLORIDA PWR CORP CRYSTAL RIVER UNIT 3 - FUEL STORAGE POOL MISSILE SHIELDS" Mu ## /f EAI'l C :;U E $

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PLANT NAME: CRYSTAL RIVER 43 REVIEWER INI TIAU XJM DISTRIBUTOR INITIAL:

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GENERAL DI'STRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

(DISTRIBUTION CODE AOO1)

FOR ACTION: BR CllIEF ORB 44 BC**W/7 ENCL INTERNAL: .i F il F:54W - te a g gWg L HANAUER**W/ ENCL CORE PERFORMANCE BR**W/ ENCL AD FOR SYS & PROJu*W/ ENCL ENGINEERING BR**W/ ENCL REACTO't SAFETY ER**W/ ENCL PLANT SYSTEMS BR**W/ ENCL EEDt*W ENCL EFFLUENT TREAT SYS**W/ ENCL J. MCOOUGH**W/ ENCL EXTERNAL: LPDR'S CRYSTAL RIVER, FL**W/ ENCL t b kth N N b ACRG CAT Da*W/16 ENCL DISTRIBUTION: LTR 40 ENCL 39 CONTROL NDR: y ?.117 -

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POWER PRODUCTION August 18, 1978

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Mr. Victor Stello, Jr.

Director Division of Operating Reactors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

SUBJECT:

Crystal River Unit 3 Operating License No. DPR-72 Docket No. 50-302

Dear Mr. Stello:

In your letter of May 17, 1978 you requested Florida Power Corporation to submit additional information concerning the movement of heavy loads near spent fuel at Crystal River Unit 3.

Florida Power Corporation hereby submits three (3) originals and forty (40) copies of our response to your request. Should you or members of your staff have any questions concerning our response, please contact this office.

Very truly yours, FLORIDA OWER CORPOR TION

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acc~ x W.P. Stewart WPS/ECS/ emf File: 3-0-3-a-3 pi-'

General Office 3201 Truny-founn street soutn . P O. Box 14042. St. Petersburg. Fionda 33733 e 813-866-5151 7go

~ . .

STATE OF FLORIDA v COUNTY OF PINELLAS W.P. Stewart states that he is the Director, Power Production, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and ,

correct to the best of his knowledge, information and belief.

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O thU W.'P. Stewart i

Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 18th day of August, 1978.

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Notary Public :

Notary Public, State of Florida at Large, My Commission Expires: July 25, 1980 L

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FPC RESPONSE iG NRC REQUEST-FOR ADDITIOi..L LNFORMATION

1. Provide a diagram which illustrates the physical relhtton between the reactor core, the fuel transfer canal, the spent fuel storage pool, and the ~ set down, rece ivi ng or storage area for any heavy- -

loads moved on the refueling floor.

Response: ,

The a t t a c h e d 'C Fy"s Ea lR i v e r U n i t ~3'FSAR Figure 1-11, Elevation 160'-0"

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and Auxiliary Buildi'g Elevation 162'-0", provides the information requested in Item 1.

2. Provide a list of all objects that are .r e q u i r e d 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 ca rrying height) and the f requency of m o v e_ m e_n t . . _ _

Response

See attached Tables 1 and 2..

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

Response

The fuel cask used at CR #3 is a one-element cask with the following weight and dimensions:

Weight -

50,000 lbs.

Overall Dimensions -

214 in. long, 50 in. diameter

4. Identify any heavy load 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: -

In response to a Request for Additional Information (see CR #3 FSAR .

Supplement, Question 9.20, Parts a through k) FPC performed a cask drop-anaylsis for CR #3. This analysis is discussed in Section 9.6 of the CR #3 FSAR and Section 9.1 of the Staff Safety Evaluation Report.

5. Identify any heavy loads'that are c a r r i .e d over equipment required for safe shutdown of a plant that is operating at the t Lme 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.

A.

c' Page 2

Response

There are no heavy loads that are carried over, equipment required for safe shutdown of the plant that la operating at the time the load la moved. .

6. If heavy. loads are required to be carried over the spent fuel storage pool or transfer canal at your factity, discuss the fea-sibility of a handling accident which would result in water leak-age severe enough to uncover the spent fuel. Describe the basis for your c onc lu s ion s .

Response

Technical Speciticaton 3.9.7 requires that loads in excess of 2,750-pounds, except for movement of the missle shield and pool divider gate as necessary for access to the fuel assemblies, be prohibited from-travel over fuel assemblies in the storge pool. The restriction on movement of loads in excess of the nominal weight of a fuel and con-trol rod assembly and associated handling tool over other fuel assem-blies in the storage pool ensures that in the event this load' is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

Technical Specification 4.9.7.1 requires that the interlocks on the Auxiliary Building overhead crane, which prevent movement of load in

excess of 2,750 lbs. over the fuel pools, be demonstrated operable.

Specification 4.9.7.2 requires that whenever the crane is operated in the cask handling mode, we must verify that no fuel assemblies are stored in the pool adjacent to the cask loading a rea and that the water-tight gate between the pools is in place and sealed.

1 In addition to the crane interlocks and administrative controfs re-quired by Technical Specifications, FPC analyzed the effects of drop- .

ping the fuel cask and subsegmently rupturing the cask loading area floor or causing. leakage from pool B. As discussed in Section 9.6.1.5 of the FSAR, this postulated event will not result in uncovering of the fuel in pool A or result in any hazard to the public.

7. Describe any design features of your facility which affect- the potential for a heavy lor inndling acc_ident involving spent fuel, e.g., utilization of a single failure proof c ra ne ,

Response

Section 9.6.1.5, Fue l llandli ng Equipmen t , of the CR #3 FSAR describes the interlock system at CR #3 which precludes the movement-of the spent fuel cask over the spent fuel pool area. This section also

.Page 3 Response * (continued) describes the administrative controls required by Technical Specifi-cations 4.9.7.1 and 4.9.7.2 as well na the conshrvative design of the Auxiliary Building overhead crane and associated equipment.

In addition to these design f e a t u 'r e s , administrative controls describ-ed in the CR #3 procedures a re placed on the use of the missile shield crane and the Auxiliary Building overhead crane to insure that heavy loads (except missile shields) are not moved over fuel assemblies stored in the spent fuel pools. The heaviest loads, other than the fuel cask, are the missile shield members. Their design is such that if dropped in the water, they will float and'will not damage the spent fuel assemblies.

8. Provide copies of all procedures cur'ently r in effect at your facility for the movement of heavyloads over the reactor core during refueling, the spent fuel storage pool, or equipment required for the safe shutdown of a plaat that is operating at the time the move occurs.

Response

The following list of procedures are enclosed:

a) SP-434, Fuel Storage Pool Missile Shields b) SP-530, Demonstration of the Auxiliary Bldg. Overhead Crane (FHCR-5) Interlock Operability c) SP-531, Spent Fuel Bridge Interlock Surveillance d) SP-532, R.B. Main & Auxiliary Briige Interlocks e) SP-601, Procedure for Load Testing Sling and Lifting Fixtures f) SP-670, R.B. Bridge Load Test g) SP-671, Spent Fuel Bridge-Load Test h) SP-672, Procedure for Load Testing New Fuel Elevator

1) FP-203, Defueling and Refueling Operations -

j) FP-401, Reactor Vessel Closure Head Removal and Replacement k) FP-402, Reactor Vessel Closure Head Stud Removal and ~

Replac,ement

1) FP-501, Reactor Interna.ls Removal and Replacement m) FP-601, Fuel Handling Equipment Operations .

n) FP-1001, Spent Fuel Handling .

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

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'Page 4 '

Response: , ,

The following discussion will address each of the eight Regulatory Positions:

A. Regulatory Position # 1 ,- S e c t i o n 9.3.2.2 of the CR #3 FSAR identifies which equipment in the spent and new fuel systems that is designed to seismic Class I requirements.'

B. Regulatory Position #2 - As discussed in Section 9.3.2.2 of the CR #3 FSAR the spent fuel pools are cove red with missile shields designed to preclude penetration of high-energy tor-nado generated missiles. Removal-and installation of these shields can only be accomplished in accordance with CR #3 Technical Specification 3.9.11. -

C. Regulatory Position #3 - Interlocks and administrative con-trols are utilized to preclude carrying loads in excess of 2750 pounds, except those loads identified in the CR #3 Technical Specification necessary for fuel handling, over stored spent fuel assemblies.

D. Regulatory Position #4 - The CR #3 spent fuel pools are en-closed within a controlled leakage building. The auxiliary building is equipped with an appropriate ventilation and filtration system to limit the potential release of adio-active materials. The CR #3 ventilation and filtration sys-tems are described in Section 9.7 of the CR #3 FSAR.

E. Regulatory Position #5 - FPC utilizes interlocks and/or ad-ministrative controls to preclude moving heavy loads

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(including the refueling' cask) not allowed by Technical Specifications, over spent fuel assemblies.

F. Regulatory Position #6 - The CR #3 spent fuel pool design meets this position statement as described in FSAR Section 9.3.

G. Regula. tory Position #7 - CR #3 has monitoring equipment

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which will alarm if the water level fall below a predeter-mined level or if high radiation level are experienced. The water level alarm will annunciate in the control room and the radiation monitor will alarm locally and in the control room. This equipment is tested in accordance with t h'e CR #3 Technical Specifications. The filtration system operates continuously. .

H. Regulatory Position #8 - The CR #3 spent fuel cooling system meets this regulatory position as described in FSAR Section 9.3.

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TABLE I LIST OF LOADS MOVED OVER REACTOR CORE ,

MOVEMENT FREQUENCY OF OBJECT WEIGHT (l'bs) SIZE PATH (I) HEICHT (ft)(2) MOVEMENT

.) Plenum Assembly **98,500 Diameter - 13'11" A to B 1 Refueling (moved twice)

Height - 10'8'

!). Rzactor Head & Studs <-300,000 Head Diameter - 16' A to C to D 30 Refueling (moved twice)-

Height - 30' Sted Diameter - 6.5" A to C to E Height - 3'

'l) Haad & Interhals a-12,000 Tri-pod 14' between F to C to A 30* Refueling (used to .a-Handling Fixture legs move head &-

10' high internals)

!i) Internals Handling Ringl*1359 '

Diameter 14' C to C to A 36 Refueling (used to re--

Adapter, Pendants & Adapter e"850 Height 6"-8" H to G "

move inter-Spreader Ring Pendants ' 791 Thickness .25" H to G .

nals onif)

5) Internals Handling - 3,400 Le ng th ' 6' I to F 40* Refueling (used to re-Extension Width 12" move head &

Height 6" internals)-

.i) Internals Indexing e-12,500 Diameter 14' G to C to A 30 Refueling (moved'twice)

Fixture Height 5'6" Thickhess .25" . -

.?) R2 actor. Head Guide ae600 Length 4' E to C to A Refueling (moved twice)

Studs Diameter 6.5" 30

'3) Cetera & Associated a- 60 Camera: C to A 30 Used throughout refuel-Ctbling Le ngth 24" ing outage Diameter 2" Cable:

, Length 40' Diameter 3/4" ,

4 I

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TABLE I (Continued)

LIST OF LOADS MOVED OVER REACTOR CORE 4 MOVEMENT FREQUENCY OF OBJECT WEIGHT (Ibs) SIZE PATH (I) HEICitT (f t)(2) HOVEMENT

9) Specimen Handling Tool <100 Diameter - 2" J to A 30 Per Tech. Spec. .

Length - 40' 4.4.9.1.2.

0) Surveillance Holder <100 Diameter - 2" A to B 2 Fer Tech. Spec.

Tube Assembly Length - 12' 4.4.9.1.2-

1) Surveillance Capsules (20 Diameter - 2" A to B 2 Per Tech. Spec.

' Length - 18" 4.4.,9.1.2

2) Long-handled Tool & <100 Diameter - 2" J to A and 30 Used throughoot Fittings Length - 40' J to B refueling

3) Fual Assemblies - 1550 Length - 14' A to B 3 Refueling (1/3 of core

. Width - 8.5" B to Pools to be replaced)

Depth - 8.5"

4) Control Rods a- 125 Le ngth - 14' A to B 3 R*efueling (move all Width

• 6" control rods)

De p t h ,-- 6" Tha internals handling extension shown on Figure 1 is pinned and safety-wired to the hook of Polar Crane. The head and internals handling fixture is pinned and safety-wired to the extension piede. This lifting arrangement then becomes an intergal part of the polar crane and is used for lif ting andmovement of the head and internals. .

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NOTES TO: TABLE'I (1) :The '. movement.~ pa tH . locatio ns~ des igna t ed in this table are'shown on Figure.1~ attached..

(2) The heights indicated are approximate heights above the R.V.

' flange. The' top of the' fuel. core is.approximately 11 feet below the. top of the fla nge .

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TABLE II LIST OF LOADS MOVED OVER SPENT FUEL STOKAGE POOLS MOVEMENT FREQUENCY OF OBJECT WEIGHT (lbs) SIZE PATH (I) HEIGHT (ft)(2) MOVEMENT

! Fu31 Assembly --1550 Length - 14' A to B Refueling Width - 8.5" J to I to C to 4 Depth - 8.5" Reactor (New Fuel)

) Transfer Carriages a- 2626 Length - 24' C to D 30 Only for. maintenance

, Width - 2' or repair j) Lifting Beam for --300 Length - 8' 33 Used for carriage Carriages Width - 8" removal .

2) Spent Fuel Cates e- 3900 Length - 28' E to F 30 Refueling - moving fuel Width - 35.5" between pools Thickness - 1"

) Missile Shields e. 8200 Length - 26' G to B to A 37 Refueling, maintenance Width - 30"

• Height - 30" .

) Niw Fuel Elevator --2080 Length - 16' H to I 37 During new fuel receipt Taat Weight Diameter- 8" l Equipment / Pe rsonnel e- 250 Length - 4' Throughout Fuel '30 During maintenance on Lifting Basket Width - 4' Pool Area pools or equipment-Height - 3' e

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NOTES'TO TABLE II .

(1) The--movement path _ locations l designated in this table are.shown on Figure 2 attached. ,

(2)- The heights indicated are approximate-maximum heights above the top of the-spent' fuel storagg racks. ,

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