ML17223A549

Revised Proposed Tech Specs Re Steam Generator Tube Repair

ML17223A549
Person / Time
Site:	Saint Lucie
Issue date:	03/08/1990
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17223A547	List: ML17223A545 ML17223A549
References
NUDOCS 9003150449
Download: ML17223A549 (9)

Text

ATTACHMENT 1 Marked-up St. Lucie Unit 1 Technical Specifications 3/4 4-5 3/4 4-8 (plus insert)

B 3/4 4-3 9003i50449 900308 05000335 PDR .AGOCK P PDC

K REACTOR COOLAh: SYSTEM STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION: d'

~at Mith one or more steam generators inoperable, restore the inoperable generator(s) to OPERABLE status prior to increasing T above 200'F.

avg SURVEILLANCE REOUIREIMENTS 4.4.5.1 Steam Generator Sample Selection. and Inspection - Each steam generator shall be determined OPERABLE during shutoown oy selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.

4.4.5.2 Steam Generator Tube Sample Selec"..'on and Inspection - The steam generator tuoe minimum sample size, 'nsoection result classification, and the corresponding action required shal'I "e as specified in Table 4.4-2.

The inservice inspec ion of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspe ted tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4. Steam generator tubes shall be examined in accordance with Apoendix IV of the ASME Boiler and Pressure Vessel Code - Section XI - "Inservice Insoection of Nuclear Power Plant Components" 1974 Edition and Addenda through Summer 1976. The tubes selected for each inservice inspection shall include at least 3'f the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:

a. Mhere experienc in similar plants with similar water chemistry indicates critical areas to be, inspected, then at least 50 of the tubes inspected shall be from these

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critical areas.

b. The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:

A11 penetrations 1

(>20 )> ~ 1 1 1 1y 1 d d 11 Tubes in tho'se areas where experience has indicated potential problems.

ST. LUCIE - UNIT 1 3/4 4<<5'gak gAuct Ho+ Scca pl~yyed a~ z/eave

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REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued f +pals/\

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t e' Oefect means an imperfection. of such severity that imi t .A tube contai ning a de feet Any, tube which does not permit the passage of the is it de eddy-exceeds fecti ve

6. ~P1 h tii<<t if current inspection probe shall be deemed a defective tube.

f which the tube shall be removed from service become i 8 unserviceable prior to the next inspection and is 8

ecause 8

it may 88$ tr equal to 40K* of the nominal tube wall thickness. s

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7. Unserviceable describes the condition of a tube if it ks 0 or contains a defect large enough to affect its structura 'l integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line XH Ocr'+ 5 break as specified in 4.4.5.3.c, above.

Afkcl.cd

8. T~bl i i p tl f 8 t .

8 tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing hrough-wall cracks) required by Table 4.4-2.

gr res'r I CPA sl" 4.4.5.5 ~Re orts Ot F 18.CV CCI S y f/C Cess'm~

a ~ Following each inservic inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Comission within 15 days.

b. The complete results of the steam generator tube inservice inspec-tion shall be included in the Annual Operating Report for the period in which this inspection was completed. This report shall include:

1. Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugge .

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• This 40% plugging limit is not applicable during the cycle 7 operation up to June 30, 1986. If at any time during this period the unit enters any Modes other than Modes 1 and 2, or Mode 3 for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the unit shall be placed in cold shutdown and the tubes with indications greater than 40% through-wall- penetration shall be removed from service prior to exceeding 200'F.

ST. LUCIE - UNIT 1 3/4 4-8 Amendment No. 73

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Inserts for page 3/4 4-8

9. ~eleevin means that tube sleeving is permitted using an approved sleeve design in areas where the sleeve spans the tube sheet area and whose lower joint is at the primary tube sheet face. Each sleeve shall be inspected at the time of installation. Subsequent inspections will be conducted in accordance with the Steam Generator Tube Sampling Selection and Inspection of Surveillance Requirement 4.4.5.2.

Insert 1 Tubes repaired with Westinghouse sleeves shall be removed from service if the sleeve imperfection depth is equal to or greater than 374 of the nominal sleeve wall thickness. Tubes repaired with Combustion Engineering sleeves shall be removed from service sleeve imperfection depth is equal to or greater than 344 of the if the nominal sleeve wall thickness.

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