ML17342B119

Requests Relief from Visual Exam Requirements of IWA-5246 for Control Rod Drive Housing D-8,per Encl Relief Request 17 for Second Inservice Insp Program Interval.Approval Requested by 880212.Fee Paid

ML17342B119
Person / Time
Site:	Turkey Point
Issue date:	02/03/1988
From:	Woody C FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
L-88-53, NUDOCS 8802090520
Download: ML17342B119 (24)

Text

ACCESSION NBR FACIL'0-250 AUTH. NAME 4lOODYI C. O.

REC lP. NAME REGULA" Y INFORMATION DISTR IBUTIO DYSTEM (BIDS) 8802090520 DOC. DATE: 88/02/03 NOTARIZED:

NO Turkey Point Planti Unit 3I Florida Poujer and Light C AUTHOR AFFILIATION Florida Power Zc Light Co.

RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

DOCKET 05000250

SUBJECT:

Requests relief from visual exam requirements for repaired control rod drive housing during inser vice insp progami second interval. Approval requested bg 880212 in order to support startup of plant follouJing repairs.

DISTRIBUTION CODE:

A047D COPIEB RECEIVED: LTR j ENCL g SIZE:

TITLE:

OR Submittal:

Inservice Inspection/Testing/Relief from ASME Code

'NOTES:

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14000, JUNO BEACH, FL 33408.0420 FEBRUAR'r 3

1888 L-88-53 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.

C.

20555 Gentlemen:

Re:

Turkey Point Unit 3 Docket No. 50-250 Request for Relief Inservice Inspection Program Second Ins ection Interval Pursuant to 10 CFR 50.55a(g)(5)(iii), Florida Power 6 Light Company (FPL) has determined that conformance with certain code requirements is impractical following repairs to Turkey Point Unit 3 control rod drive housing D-8.

Accordingly, FPL requests relief from the visual (VT-2) examination required by IWA-5246, "Repaired or Replaced Components and Alteration of a System," of Section XI of the ASME Boiler and Pressure Vessel Code Rules for Inservice Inspection of Nuclear Power Plant Components.

The basis for relief is provided in the attached Relief Request No.

17.

A similar request for relief was approved by the NRC Staff by letter dated June 25, 1987.

Your approval is requested by February 12, 1988 in order to support the startup of Turkey Point Unit 3 following repairs, currently scheduled for that date.

In accordance with 10 CFR 170.12(c),

an application fee (FPL Check No. 7154) for $150.00 is attached.

IF there are any questions, please contact us.

Very truly yours, C

~

~

~

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C. 0.

oody Exec ive Vice President COW/TCG/gp Attachment cc:

Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey. Point Plant TCG/003.III gee > a/~~~

8SOao9a52o 88O2OS PDR ADDCf( 05000250I

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TURKEY POINT PLANT UNIT NO.

3 INSERVICE INSPECTION SECOND INSPECTION INTERVAL RELIEF REQUEST NO.

17 A.

COMPONENT IDENTIFICATION CLASS 1

REACTOR PRESSURE VESSEL CONTROL ROD DRIVE LOHER CANOPY SEAL HELD NO. D-8 EXAMINATION CATEGORY:

B-0 EXAMINATION ITEM NUMBER:

B14.10 EXAMINATION DESCRIPTION:

PRESSURE RETAINING HELDS IN CONTROL ROD DRIVE HOUSINGS B.

EXAMINATION REQUIREMENTS IHB-2500-1, Perform volumetric or surface examination of 10% of the peripheral control rod drive housingq during the inspection interval.

Drawing number MCI-CRD-004 provides the examination requirements for a typical CRDM housing weld.

IHA-7530 and IHA-4500, requires prior to return of the plant to service, and following a repair or replacement a

preservice inspection shall be performed.

IHA-5000, after repairs by welding on the pressure retaining

boundary, a

system hydrostatic pressure test shall be performed.

IHA-5246, The visual (VT-2) examination following a repair or replacement of a component, the examination may be limited to the repaired or replaced component, but shall include any connection made to the existing system.

C.

RELIEF REQUESTED FPL requests relief from the visual (VT-2) examination requirements of the repaired control rod drive housing number D-8.

D.

BASIS FOR RELIEF 1.

LOCATION The location of the CRDM two (2) piece split canopy seal is located in the third (3) row from the outer peripheral of the Reactor Pressure Vessel closure head.

Drawing number MCI-CRD-003 color coded in red, provides the location of the repaired housing weld number D-8.

TURKEY POINT PLANT UNIT NO.

3 INSERVICE INSPECTION SECOND INSPECTION INTERVAL RELIEF REQUEST NO.

17

2. INITIALPREPARATION FOR EXAMINATION In order to perform the initial visual examinations, the following preparations had to be performed:

a.

The visual inspection/examination ports in the shroud were removed.

See drawing number MCI-CRD-009 for detail of ports, and drawing number MCI-CRD-003 for location in shroud of all three (3) ports.

b. Radiation surveys were conducted prior to performance of examinations, See attached survey for radiation doses.

c.

Remote visual examination equipment were lowered down in the cavity in order to video tape results.

3. INITIAL EXAMINATIONS The identification of the leaking CRDM was identified by an inspection through the recently installed inspection/examination ports.

Visual (VT-1) examinations using the remote visual equipment confirmed the location of the leak and identified the indication at 180 degrees (backside) of the CRDM housing.

In addition to the confirmation of the leaking CRDM an additional sample of eight (8)

CRDM were also

examined, in order to bound in the area.

The Remote Visual examinations identified above resulted in a exposure of 3950 mr to the examiners.

4.

REPAIR The repair of the leaking CRDM Lower canopy seal weld will consist of encapsulating the entire weld with a two (2) piece split ring.

See drawing number MCI-CRD-002 for original detail.

This two (2) piece split ring will be welded to the CRDM housing and the instrument port by a fillet weld running 360 degrees around the top and bottom of the ring.

See drawing number MCI-CRD-007 for details The second piece will be welded by two (2) long welds (open butt).

These welds will be facing the outer peripheral of the closure head such that a partial examination can be performed through the inspection ports during

'the pressure test

TURKEY POINT PLANT UNIT NO.

3 INSERVICE INSPECTION SECOND INSPECTION INTERVAL RELIEF REQUEST NO.

17 The examinations performed during the repair activity will consist of in process visuals and visuals and surface examination of the completed welds and a

Remote visual examination of the repair area taped to establish a

baseline.

The surface examination performed after the repair will satisfy both the construction and section XI ASME Codes.

5.

ACCESSIBILITY DURING SYSTEM PRESSURE TESTS The following restrictions prohibit 100% direct or remote visual (VT-2) examination of the entire repair weld during the pressure test:

a.

The installation of the CRDM Coil stacks and the RPI cables prohibit entry from the top of the head.

b.

Access to the CRDM is limited by the CRDM ports being eight and one half inches (8 1/2") away from each other.

c.

The test temperature and test pressure 2350 psi, 547 degrees prohibit direct examination of the repair area.

d.

The radiation doses.

See radiation survey 6.

ADDITIONAL COMMENTS In addition to the above obstructions, the amount of associated effort and supporting work to comply with the ASME code requirements is not justified for the following reasons:

a.

The design configuration of the encapsulating canopy ring will provide assurance of an acceptable level of Quality and Safety.

Drawing no.

MCI-CRD-007.

b.

FPL feels that with the design of the split ring and the examinations performed coupled with the VT-2 examination through the inspection/examination ports that an acceptable level of Quality and Safety will be assured.

c.

FPL feels that with the addition of the three (3) inspection

ports, early identification of leaks from the CRDM ports will assure a

continued acceptable level of quality and significantly reduse the radiation exposure to personnel.

II

TURKEY POINT PLANT UNIT NO.

3 INSERVICE INSPECTION SECOND INSPECTION INTERVAL RELIEF REQUEST NO.

17 d.'PL feels that the removal of the above obstructions solely for the purpose of viewing the repair welds by the visual examination method coupled with the large expenditures of manhours and man-rem that will be required with essentially no compensating increase in plant safety.

E.

ALTERNATE EXAMINATIONS

1. Perform the Visual (VT-2) examinations during the Reactor Coolant System overpressure test to the extent practical.

2. Perform these examinations through the visual inspection/examination ports and with the use of a

high intensity

light, these viewing ports will provide the inspector/examiner with a

means of locating and identifying leaks that may be present during the overpressure test F.

IMPLEMENTATION SCHEDULE The third refueling outage of the second

period, of the second ten-year inservice interval.

G.

ATTACHMENTS inspection inspection DRAHING NUMBER MCI-CRD-002 DESCRIPTION CRDM LONER CANOPY SEAL HELD ORIGINAL DESIGN MCI-CRD-003 ISI CONFIRMED LEAKER & INITIAL SAMPLE MCI-CRD-004 CLOSURE HEAD HOUSING DETAIL TYPICAL MCI-CRD-007 SPLIT THO PIECE CANOPY RING MCI-CRD-009 "VISUAL OBSERVATION/EXAMINATIONPORTS RADIATION SURVEYS OF TURKEY POINT PLANT REACTOR PRESSURE VESSEL CLOSURE HEAD.

J

REFERENCE DRAuIHGSI REVE PRESSURE I

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