ML20010A230

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Tech Spec Section 3.2.5 Re Concrete & Structural Steel
ML20010A230
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 03/31/1980
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML20010A217 List:
References
NUDOCS 8108110202
Download: ML20010A230 (2)


Text

+ . ATTACHMENT 2 ' l SGRR

g. Service air piping
h. Primary service water piping

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Location of cut areas for reactor coolant system, main steam system, and main feedwater system are shown on Figures 3.2-1, 3.2-2, and 3.2-3,

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7, respectively. As appropriate the open ends of cut piping will be covered to ensure cleanliness during the repair.

The governing overall code for the steam generator replacement shall be the ASME Section XI, 1977 Edition with addenda through the sumner of 7 1978. '*

y . . . . , - , a.- . -n-3.2.5 Concrete and Structural Steel The following structures or portions of structures within the containment will be removed to provide a path for the lower assenbly (refer to Figures 3.2-4 through 3.2-6 for illustration):

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a. A section of the steam generator "C" shield wall above eleva-tion + 58' for Unit 4. A .section of the steam generator "A" shield wall above elevatfig + 58' for Unit 3.
b. A section of the operating floor concrete at elevation + 58' including a steam generator "A" upper support embed for Unit 2 and steam generator "C" thrust beam for Unit 4
c. The rcncychle secondary shield wall panels cppesite the contain- -

nent equipnent hatch fres elev:tien + 30'-6" to elevatien + 5S',

and an cdditicnal width of secendary shic1d wall oppcsite tha equiptent hatch frc: elevatien + 30'-6" to elevation + 5S' d.

A pcrtion 'of the fleor framing cnd grating at elevctic: + 5S' chcra the equip =ent hctch

e. A portion of .the floor fre-4ng and recevable floor slabs at elevation + 30'-6" at the leu point of the equipnent hatch
f. The upper portion of the steel stairway near the equipeent hatch opening
g. A reinforced grouted pad in the equip =ent hatch at elevatien

+ 30'-6"

h. A portion of the truss system tie rods to allow for clearance of the temporary polar crane trolley. (The truss system was originally utilized in the constructicn of the contain=ent and dees not perform any structural related function at present.)

8108110202 810807 PDRADOCK05000hk 3-9 Revision 7

,G March 1980 r

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1. A portion of tha equipment Tatch sleeve at elevation +30'-6".

(A small section of t.he steel sleeve will be replaced with thicker steel to assure load transfer to the supporting concrete wall during ingress and egress of heavy equipment. The affected portion of steel to be replaced does not form a part of the 7 containment pressure boundary nor affects the structural integrity of the containment.)

3.2.5.1 Removal of Concrete Structures Removal of bulk volumes of containment inc.ernal structura1 con' crete will --

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utilize equipment and techniques commercially ava' liable. 4 e' intent is d' i

3-9a Revision 7 March 1980 i

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TELECO?Y D te l Turkey Point Plant SECT: Tic /cso By ~ &ify July 13,1981 TO: Kr. J. P. O'Reilly, Director, Region II Office of Inspection and Enforcea. cat U. S. thclear P.egulatory Ccenission Atlani.c. Georgia 30303 FR0ft: Mr. J. X. Hays, Plant Manager - Nuclear . - -

Turkey Point Plant - DPR 31 and 41 ,

Florida Pmer and Light company Miati Florida

SUBJECT:

ME)G FOR FACSIHI!.E TRAMSMISSION TO CO'(FIRM .

REPD?. TABLE OCCURREliCE 250-81-13 - - -

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This ra_.co confires our telephor.e notification of the subject proept notification reportable occurrence nade Friday, July in,1981, to your Duty Otficer, Mr.1. Villaiva as follees:

OCDEEK^E - Da Fricay, Jul,/ 10, 1981, a relatively sr.all void Tiscovered in the coacrete inrediately below the equipent hatch ,

berrel was deterninM to be repartable in accordance with technical ~

sp:cification 6.9.2.a.(9). This void tras found in the course of rakin2 scoe alterations at the equipunt hatch to facilitate handling equipent and large cccpomnts during the steua generator rt.-pair effort.

CO2RECTIVE ACTION - Unit 3 is presently defueled and undert.oing inservice insp?ction of the reactor vessel. Prior to restarting the unit an er.ginscring evaluation (currer,tly in progress) and any

, rccessary repairs vill be capleted. A plan for inspection of the l sa.:e area on Unit 4 is pending cocpletien of the engineering i cyaluation.

AA FE aar l JtH:ca ')\ L l

W hE oc 13 b J6 h ecom.s . . . sEnvn4 PEOPLE

ATTACHMENT 4

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  • tween reen a ucnr covn.w July 24,1991 PRK-LI-81-351

( Kr. James P. O'Reilly, Director, Region II - . -

Office of Inspection and Erforcesent U.S. Nuc1 car Re,ulctory Cealssion .  ;

101 Marietta Str.,c'., suite 3100 1,tlanta, Georgia 30303

Dear Mr. O'Reilly:

REPORTABLE DCCURRE!CE 250-81-13

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TURKEY P01HT UNIT 3 '  ;

DATE OF OCClTARENCE: JULY 10,1981 TECHRIC11 SPECIFICATION 6.9.2.a.9 '

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CONTAltEEtc STRtfCTURE Tlie attached 1.icensae Event Report is being suts:ii. Led in eccordance with Technical Specification G.9 to provida pra:gt notiffcation of the subject occurrence. -

Very truly yours, g .-

c e A.D. Schaldt s

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Vice President E .ng j{

' Power Resources 4 E

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cc: Director, Office of Inspection and Enforcsont (40)

Harold F. Reis. Esquire h

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, ,,,g by the construction crew. This was determined to be reportable in I g [.tccordance with Technical Specification 6.9.2.A. (9). _

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, this tin to detereina r.2thod of repair. A fo11ov e,> report vill be

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