L-2006-152, NRC Order EA-03-009 - Reactor Vessel Head and Vessel Head Penetration Nozzle Inspection Results SL2-16

NRC Order EA-03-009 - Reactor Vessel Head and Vessel Head Penetration Nozzle Inspection Results SL2-16

ML062300039
Person / Time
Site:	Saint Lucie
Issue date:	08/10/2006
From:	Johnson G Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
EA-03-009, L-2006-152
Download: ML062300039 (15)

Text

Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 0 August 10, 2006 F=PL L-2006-152 10 CFR 50.4 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: St. Lucie Unit 2 Docket No. 50-389 NRC Order EA-03-009 - Reactor Vessel Head and Vessel Head Penetration Nozzle Inspection Results SL2-16 In April 2006, St. Lucie Unit 2 commenced refueling outage SL2-16. Based on the results of the visual examinations, UT examinations, supplemental OD NDE and leak path assessments (including ECT of the vent), FPL concludes that the RVHP nozzles are not degraded and no wastage has occurred of the RPV head.

In accordance with Section IV.E of the NRC Order (EA-03-009), the attachment submits the FPL inspection results for St. Lucie Unit 2 for the spring 2006 refueling outage (SL2-16).

Please contact Ken Frehafer at (772) 467-7748 if there are any questions about this submittal.

Very truly yours, GLJ/KWF Attachment Alo(

an FPL Group company

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 1 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 FIRST REVISED NRC ORDER EA-03-009:

REACTOR PRESSURE VESSEL HEAD AND VESSEL HEAD PENETRATION NOZZLE POST REFUELING OUTAGE INSPECTION RESULTS FOR ST. LUCIE UNIT 2 - Spring 2006 The First Revised NRC Order EA-03-009 [i] was issued on February 20, 2004, establishing interim inspection requirements for reactor pressure vessel heads of pressurized water reactors.

In Section IV.E. of the NRC Order, the NRC required that the results of the inspection be provided within 60 days of the plant being returned to operation. Florida Power and Light Company (FPL) hereby submits the inspection results for St. Lucie Unit 2 (PSL-2) for the spring 2006 (SL2-16) refueling outage (RFO).

St. Lucie Unit 2 Spring 2006 (SL2-16) Post Outage Reactor Vessel Upper Head Inspection Results:

1. Plant Susceptibility Category:

The St. Lucie Unit 2 reactor pressure vessel (RPV) closure head had approximately 16.3 effective degradation years (EDY) at the start of the Spring 2006 refueling outage. The inspection category identified in the Order is High. The corresponding inspection method for the High Category is specified in Section IV.C.(1) of the NRC Order.

2. Inspection Scope and Method:

2.a. RPV Bare Metal Head Surface Visual: A bare metal visual inspection (VT) of the RPV head top surface, including 3600 around each RPV head penetration nozzle, was performed in accordance with section IV.C.(5)(a) of the NRC Order and supplemented by Relaxation Request Number 4 ["1 approved by the NRC on December 27, 2004 and January 10, 2005.

[".." [Iv] The VT was performed under the insulation by delivering a video probe under the shroud support ring after removal of flashing panels. Limitations to the bare metal visual inspection were identified in the Relaxation Request. ["I These limitations included a partial area under 32 insulation support feet (<118 square inches) and the inaccessible areas under the -2 1/4" wide vertical leg of the reflective metal insulation that contacts the twelve 6-inch wide shroud lugs. In addition, the areas inside the 54 RV stud holes were limited. The total area of limitation is less than 1% of the total reactor vessel head surface area available for inspection.

2.b. RPV Head Penetration Non Visual Inspection: The ultrasonic (UT) examination technique option, identified in section IV.C.(5)(b)(i) of the First Revised NRC Order, was performed on all of the 102 reactor vessel head penetration (RVHP) nozzles, including the vent line. The examination area was planned to meet the NRC Order required area for the ICI, vent and previously repaired CEDM penetrations. For the 86 CEDMs with the original threaded guide cone configuration, the inspection was planned to include the nozzle base material 2 inches above the J-groove weld to the bottom of the weld. However, below the weld the UT

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 2 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 examination was planned to the maximum extent possible. If the area below the weld coverage was less than 0.50 inches, non visual NDE from the outside diameter (OD) would be used to extend the coverage to the maximum extent possible, but not less than 0.50 inches below the weld toe. The methods used for the OD NDE were automated UT and manual PT. The limitations associated with the threaded guide funnels in the original CEDM penetrations were the subject of Relaxation Request Number 3 [ii] and corresponding NRC approval [iii&iv] of the relaxation.

As part of the UT examinations, the 101 RVHPs with interference fits were assessed to determine if leakage had occurred into the interference fit zone (annulus between the RPV head and the penetration above the pressure boundary weld). This assessment used the Areva/Framatome-ANP proprietary "leak path" technique, which was described in the post outage inspection report for a previous FPL St. Lucie Unit 1 RPV head inspection. [v)

The UT inspection procedure and essential variables used on the 101 RVHPs with interference fits has been demonstrated as part of the industry demonstration program conducted by the EPRI NDE Center. The personnel qualification requirements that were described in Reference [vi remain unchanged.

An eddy current examination (ECT) was performed on the vent nozzle weld surface to ensure weld integrity in lieu of the UT method to assess if leakage has occurred into the clearance fit annulus between the vent nozzle and RPV head steel. The ECT procedure had been successfully demonstrated on RVHP J-groove attachment welds as part of the industry demonstration program conducted by the EPRI NDE Center. All essential variables (Examination Technique Specification sheets, ETSS) and procedural requirements used during the vent nozzle weld examination remained essentially the same as those previously demonstrated.

3. Inspection Results Summary:

3.a. RPV Head Visual Results: The overall condition of the St. Lucie Unit 2 RPV head surface was clean with no evidence of leakage occurring from the RV head to penetration interface of the 102 RVHPs. No wastage or boric acid buildup was observed on the reactor vessel head surface.

Some thin film boric acid stains were observed on the vertical surfaces and insulation overhead of penetrations #2, 13, 49, 51, 74, and 83, and in-core instrument (ICI) column # 97. The thin film nature of the stains and lack of buildup is indicative of non operational leakage. The source of the stains was attributed to CEDM venting and past ICI column leakage prior to startup.

There was no degradation of the RPV head surface associated with the boric acid stains. These conditions were addressed as part of our boric acid corrosion control program and the corrective action program.

3.b. RPV Head Penetration Non Visual Inspection Results: There were no relevant indications identified by the ID UT in any of the 102 RVHPs in the St. Lucie Unit 2 RPV head.

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 3 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 Supplemental OD NDE was required on 17 CEDM nozzles to obtain the required examination area of 0.50 inches below the weld. The OD NDE method included UT and manual dye penetrant (PT). A limitation was experienced on 15 CEDM nozzles, where the OD UT was utilized to extend the coverage below the weld toe. These limitations were caused by lift off at the funnel plug weld on the high hillside of the nozzle. The small lift off limitations were > 3.80 inches below the weld toe. The supplemental OD NDE (UT and PT) did not reveal any relevant indications. The details of the ID coverage, supplemental OD coverage, and limitations associated with the funnel plug weld are described in Tables 1 and 2 and Figure 1.

An assessment to determine if leakage has occurred into the interference fit zone was performed for the 101 interference fit RVHPs. There was no evidence of a "leak path" signature for any of the 101 interference fit RVHPs examined. The "leak path" assessment is performed using the Areva/Framatome-ANP demonstrated method that utilizes UT in the interference fit zone above the pressure boundary weld. The assessment results are confirmed by the results of the bare metal visual examination. Since the vent line is a clearance fit nozzle, the clean visual examination provides a direct determination that no leakage has occurred into the annulus.

However, as an added conservatism, the flush pressure boundary surface inside of the RPV head associated with the vent line (the head vent line, alloy 600 attachment weld, and a portion of the adjacent stainless steel clad weld) was examined using a surface eddy current examination (ECT) method. The reporting criteria utilized for the ECT examination was to report all indications.

The acceptance criteria utilized for this ECT examination was "no identified flaws or degradation." There were no flaws or degradation detected by the ECT technique in the inspected area of the weld associated with the head vent nozzle. This examination provides additional confirmation for the assessment that the vent nozzle has no leakage into the annulus.

4. Corrective Actions:

With no indications of cracking in the penetrations and no evidence of boric acid buildup associated with pressure boundary leakage, no corrective actions were required to address the integrity of the reactor vessel upper head and penetrations.

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 4 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 5.

Conclusion:

FPL has met the requirements of the First Revised NRC Order (EA-03-009) as modified by NRC approved relaxation requests [iii&iv] for the St. Lucie Unit 2 Spring 2006 refueling outage by performing the required RPV head inspection.

Based on the results of the visual examinations, UT examinations, supplemental OD NDE, leak path assessments (including ECT of the vent), FPL concludes that the RVHP nozzles are not degraded, and no wastage has occurred of the RPV head.

i US NRC Letter EA-09-009, "Issuance Of First Revised NRC Order (EA-03-009) Establishing Interim Inspection Requirements For Reactor Pressure Vessel Heads At Pressurized Water Reactors," from William Borchardt (NRC) to all Pressurized Water Reactor Licensees, Dated February 20, 2004.

" FPL letter L-2004-095, "St. Lucie Unit 2, Docket No. 50-389, Order (EA-03-009) Relaxation Requests 3 and 4, Examination Coverage of Reactor Pressure Vessel Head Penetration Nozzles," W. Jcfferson to NRC, May 6, 2004.

6"US NRC Letter (Adams Accession No. ML043430268), "St. Lucie Plant, Unit 2, First Revised Order EA-03-009 Relaxation Requests No. 3 Regarding Examination Coverage of Reactor Pressure Vessel Hlead Penetration Nozzles, and Relaxation Request No. 4 Regarding Examination Coverage of Reactor Pressure Vessel Head Bare Metal Visual Examination, (TAC Nos. MC3107 and MC3 108)," E. M. Hlackett (NRC) to J.A.

Stall, December 27, 2004.

V US NRC Letter (Adams Accession No. ML050070085), "St. Lucie Plant, Unit 2, Correction to NRC Safety Evaluation for First Revised Order EA-03-009 Relaxation Requests No. 3 Regarding Examination Coverage of Reactor Pressure Vessel Hlead Penetration Nozzles, (TAC No.

MC3107)," E. M. Hackett (NRC) to J.A. Stall, January 10, 2005.

V FPL letter L.-2002-233, "St. Lucie Units I and 2, Docket Nos. 50-335, 50-389, Reactor Pressure Vessel [lead (RPVH Inspection, NRC Bulletin 2002-02 Supplemental Response," D. E. Jernigan to NRC, November 21, 2002.

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 5 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 "A"R B"Coverage Limitations Due to Funnel Plug Weld C > 0 E o > ID ID ID 0 0 Coverage Coverage Coverage Q '4 I

'a 3: below below above -- . 0 0 0." weld on weld on weld on X M

" M. downhill uphill uphill a.) 0 0 side of side of side of Axial weld weld weld Angular Extent Extent Comments (in.) (in.) (In.) (deg.) Min Max Total (in.)

CEDM 1 0.5 1.02 1.02 4.44 360 n/a n/a n/a n/a NO NRI YES CEDM 2 0.5 1.08 1.79 4.31 360 n/a n/a n/a n/a NO NRI YES CEDM 3 0.5 1.09 1.85 4.09 360 n/a n/a n/a n/a NO NRI YES CEDM 4 0.5 0.91 2.02 4.07 360 n/a n/a n/a n/a NO NRI YES CEDM 5 0.5 0.90 1.97 4.36 360 n/a n/a n/a n/a NO NRI YES CEDM 6 0.5 1.02 2.20 4.23 360 n/a n/a n/a n/a NO NRI YES CEDM 7 0.5 0.91 2.15 4.09 360 n/a n/a n/a n/a NO NRI YES CEDM 8 0.5 0.79 2.21 3.40 360 n/a n/a n/a n/a NO NRI YES CEDM 9 0.5 0.90 2.44 2.92 360 n/a n/a n/a n/a NO NRI YES CEDM 10 0.5 0.91 2.44 3.86 360 n/a n/a n/a n/a NO NRI YES CEDM 11 0.5 0.78 2.26 3.74 360 n/a n/a n/a n/a NO NRI YES CEDM 12 0.5 0.91 2.55 4.00 360 n/a n/a n/a n/a NO NRI YES CEDM 13 0.5 1.10 2.67 3.90 360 n/a n/a n/a n/a NO NRI YES CEDM 14 0.5 0.90 2.38 3.14 360 n/a n/a n/a n/a NO NRI YES CEDM 15 0.5 1.02 2.55 4.12 360 n/a n/a n/a n/a NO NRI YES CEDM 16 0.5 0.91 2.62 4.19 360 n/a n/a n/a n/a NO NRI YES CEDM 17 0.5 1.03 2.56 4.05 360 n/a n/a n/a n/a NO NRI YES CEDM 18 0.5 6.10 6.10 6.40 360 n/a n/a n/a n/a NO NRI YES Previous IDTB Repair CEDM 19 0.5 1.08 2.20 4.17 360 n/a n/a n/a n/a NO NRI YES CEDM 20 0.5 0.84 2.91 3.30 360 n/a n/a n/a n/a NO NRI YES CEDM 21 0.5 0.95 2.91 2.81 360 n/a n/a n/a n/a NO NRI YES

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 6 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 A" foci@ Coverage Limitations Due to

""Bv. ."Funnel Plug Weld

.E >

" o ID ID ID 0 £ o0 0 Coverage Coverage Coverage ' 7U

• *o - below below above - 0. 40 0 0 weld on weld on weld on

. M. downhill uphill uphill .  :

M 0 side of side of side of Axial weld weld weld Annular Extent Extent Comments (in.) (in.) (in.) (deg.) Mmn Max Total (in.)

CEDM 22 0.5 0.96 3.02 3.54 360 n/a n/a n/a n/a NO NRI YES CEDM 23 0.5 0.67 2.85 3.69 360 n/a n/a n/a n/a NO NRI YES CEDM 24 0.5 0.79 2.79 3.36 360 n/a n/a n/a n/a NO NRI YES CEDM 25 0.5 0.83 2.97 3.00 360 n/a n/a n/a n/a NO NRI YES CEDM 26 0.5 0.75 2.85 3.91 360 n/a n/a n/a n/a NO NRI YES CEDM 27 0.5 6.10 6.10 8.30 360 n/a n/a n/a n/a NO NRI YES Previous IDTB Repair CEDM 28 0.5 0.85 3.15 3.41 360 n/a n/a n/a n/a NO NRI YES CEDM 29 0.5 0.91 3.03 3.24 360 n/a n/a n/a n/a NO NRI YES CEDM 30 0.5 0.90 3.20 3.00 360 n/a n/a n/a n/a NO NRI YES CEDM 31 0.5 1.02 3.21 3.90 360 n/a n/a n/a n/a NO NRI YES CEDM 32 0.5 5.10 5.10 6.02 360 n/a n/a n/a n/a NO NRI YES Previous IDTB Repair CEDM 33 0.5 0.85 3.09 3.96 360 n/a n/a n/a n/a NO NRI YES CEDM 34 0.5 0.84 3.08 3.98 360 n/a n/a n/a n/a NO NRI YES CEDM 35 0.5 0.79 3.03 3.83 360 n/a n/a n/a n/a NO NRI YES CEDM 36 0.5 0.67 3.32 3.02 360 n/a n/a n/a n/a NO NRI YES CEDM 37 0.5 0.85 3.56 2.70 360 n/a n/a n/a n/a NO NRI YES CEDM 38 0.5 0.90 3.44 2.40 360 n/a nfa n/a n/a NO NRI YES CEDM 39 0.5 0.85 3.50 2.99 360 n/a n/a n/a n/a NO NRI YES CEDM 40 0.5 0.90 3.56 3.60 360 n/a n/a n/a n/a NO NRI YES CEDM 41 0.5 0.50 3.27 3.38 360 n/a n/a n/a n/a NO NRI YES CEDM 42 0.5 0.73 3.44 3,49 360 n/a n/a n/a n/a NO NRI YES

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 7 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 Coverage Limitations Due to "A "B" "C" Funnel Plug Weld

> "o ID ID ID o U E0 0 Coverage Coverage Coverage 0 3:0 below weld on below weld on above weld on I-L c.

t5

• 5co downhill uphill uphill .

• side of side of side of Axial n, weld weld weld Angular Extent Extent Comments (in.) (in.) (In.) (deg.) MIn Max Total (In.)

CEDM 43 0.5 0.73 3.32 3.30 360 n/a n/a n/a n/a NO NRI YES CEDM 44 0.5 0.80 3.79 2.70 360 n/a n/a n/a n/a NO NRI YES CEDM 45 0.5 0.84 3.97 5.96 360 n/a n/a n/a n/a NO NRI YES CEDM 46 0.5 0.60 3.67 3.16 360 n/a n/a n/a n/a NO NRI YES CEDM 47 0.5 0.62 3.79 3.57 360 n/a n/a n/a n/a NO NRI YES CEDM 48 0.5 0.62 3.73 3.04 360 n/a n/a n/a n/a NO NRI YES CEDM 49 0.5 0.70 3.91 2.90 360 n/a n/a n/a n/a NO NRI YES CEDM 50 0.5 0.62 3.86 5.33 360 n/a n/a n/a n/a NO NRI YES CEDM 51 0.5 0.73 4.09 5.80 360 n/a n/a n/a n/a NO NRI YES CEDM 52 0.5 0.55 4.03 3.79 360 n/a n/a n/a n/a NO NRI YES CEDM 53 0.5 0.50 3.79 3.80 360 n/a n/a n/a n/a NO NRI YES CEDM 54 0.5 0.43 3.91 4.10 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 144 207 63 0.07 n/a NRI OD UT Scan, See Table 2 for details CEDM 55 0.5 0.67 3.80 3.11 360 n/a n/a n/a n/a NO NRI YES CEDM 56 0.5 7.30 7.30 7.00 360 n/a n/a n/a n/a NO NRI YES Previous IDTB Repair CEDM 57 0.5 0.91 3.97 2.83 360 n/a n/a n/a n/a NO NRI YES CEDM 58 0.5 0.85 4.26 3.47 360 n/a n/a n/a n/a NO NRI YES CEDM 59 0.5 0.32 3.80 3.79 360 n/a n/a n/a n/a NO NRI YES IDUT to be Supplemented by OD UT n/a n/a n/a n/a 169 229 60 0.18 n/a NRI OD UT Scan, See Table 2 for details CEDM 60 0.5 0.73 4.21 2.85 360 n/a n/a n/a n/a NO NRI YES CEDM 61 0.5 0.60 4.14 2.46 360 n/a n/a n/a n/a NO NRI YES

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 8 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 Coverage Limitations Due to

""~ "B" "C" Funnel Plug Weld V M "E D 00 D I >

S o

• 0 Coverage Coverage Coverage 0 V below below above -. 0 ,

C 0 0 weld on weld on weld on I. z 2-6 to downhill 1.

uphill uphill 0 M side of side of side of Axial weld weld weld An ular Extent Extent Comments (in.) (In.) (In.) (deg.) Min Max Total (In.)

CEDM 62 0.5 0.68 4.44 5.25 360 n/a n/a n/a n/a NO NRI YES CEDM 63 0.5 0.79 4.32 3.38 360 n/a n/a n/a n/a NO NRI YES CEDM 64 0.5 0.96 4.38 3.25 360 n/a n/a n/a n/a NO NRI YES CEDM 65 0.5 0.61 4.38 3.54 360 n/a n/a n/a n/a NO NRI YES CEDM 66 0.5 0.44 4.08 3.68 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 166 220 54 0.06 n/a NRI OD UT Scan, See Table 2 for details CEDM 67 0.5 0.73 4.20 3.00 360 n/a n/a n/a n/a NO NRI YES CEDM 68 0.5 0.70 4.98 2.97 360 n/a n/a n/a n/a NO NRI YES CEDM 69 0.5 0.56 4.80 3.40 360 n/a n/a n/a n/a NO NRI YES CEDM 70 0.5 0.43 4.68 4.80 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 146 207 61 0.07 n/a NRI OD UT Scan, See Table 2 for details CEDM 71 0.5 0.67 4.85 4.62 360 n/a n/a n/a n/a NO NRI YES CEDM 72 0.5 3.66 3.66 3.71 360 n/a n/a n/a n/a NO NRI YES Previous IDTB Repair CEDM 73 0.5 0.56 4.97 3.80 360 n/a n/a n/a n/a NO NRI YES CEDM 74 0.5 0.61 5.09 3.31 360 n/a n/a n/a n/a NO NRI YES CEDM 75 0.5 0.43 4.26 3.70 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 157 208 51 0.07 n/a NRI OD UT Scan, See Table 2 for details CEDM 76 0.5 0.61 5.20 3.87 360 n/a n/a n/a n/a NO NRI YES CEDM 77 0.5 0.43 4.97 3.82 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 138 192 54 0.07 n/a NRI OD UT Scan, See Table 2 for details CEDM 78 0.5 0.56 4.85 3.71 360 n/a n/a n/a n/a NO NRI YES

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 9 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16

.1A"1 BCoverage Limitations Due to "B" Funnel Plug Weld "V E'o > 4)E 0 f ID ID ID 0 Eo Coverage Coverage Coverage 13 4)~ O~ below below above d0. 4) 0 04)E weld on weld on weld on d -, U)

U

. *.m downhill uphill uphill .

4 side of side of side of Axial weld weld weld An ular Extent Extent Comments (in.) (in.) (In.) (deg.) Min Max Total (in.)

CEDM 79 0.5 0.43 4.68 3.40 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 117 211 94 0.07 n/a NRI OD UT Scan, See Table 2 for details CEDM 80 0.5 0.44 4.80 3.50 360 n/a n/a n/a n/a NO NRI YES IDUT to be Supplemented by OD UT n/a n/a n/a n/a 161 220 59 0.06 n/a NRI OD UT Scan, See Table 2 for details CEDM 81 0.5 0.48 4.62 3.30 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 150 208 58 0.02 n/a NRI OD UT Scan, See Table 2 for details CEDM 82 0.5 0.50 5.21 2.82 360 n/a n/a n/a n/a NO NRI YES CEDM 83 0.5 0.43 4.91 3.14 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 156 212 56 0.07 n/a NRI OD UT Scan, See Table 2 for details.

CEDM 84 0.5 0.61 5.20 3.19 360 n/a n/a n/a n/a NO NRI YES CEDM 85 0.5 0.45 4.97 3.58 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 139 197 58 0.05 n/a NRI OD UT Scan, See Table 2 for details CEDM 86 0.5 0.40 4.86 3.19 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 151 206 55 0.10 n/a NRI OD UT Scan, See Table 2 for details CEDM 87 0.5 0.34 4.91 3.10 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 149 200 51 0.16 n/a NRI OD UT Scan, See Table 2 for details CEDM 88 0.5 0.32 5.80 3.00 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 145 209 64 0.18 n/a NRI OD UT Scan, See Table 2 for details CEDM 89 0.5 0.20 5.62 2.56 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT n/a n/a n/a n/a 135 188 53 0.30 n/a NRI OD UT Scan, See Table 2 for details CEDM 90 0.5 0.49 6.33 3.34 360 n/a n/a n/a n/a NO NRI YES ID UT to be Supplemented by OD UT

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 10 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 Coverage Limitations Due to "B" (D Funnel Plug Weld 0 = > ID ID ID o E

.2 °0 Coverage Coverage Coverage W o

0  : below below above -

S 0 00 weld on weld on weld on I z .-

• m j;'U6 downhill uphill uphill .

side of side of side of Axial weld weld weld Angular Extent Extent Comments (In.) (in.) (In.) (deg.) Min Max Total (in.)

n/a n/a n/a n/a 159 213 54 0.01 n/a NRI OD UT Scan, See Table 2 for details CEDM 91 0.5 0.32 5.51 3.28 360 n/a n/a n/a n/a NO NRI YES IDUT to be Supplemented by OD UT I n/a n/a n/a n/a 169 223 54 0.18 n/a NRI OD UT Scan, See Table 2 for details ICI 92 N/A n/a n/a 4.78 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 93 N/A n/a n/a 3.40 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 94 N/A n/a n/a 4.15 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 9 N/A n/a n/a 3.90 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head

____ N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 96 N/A n/a n/a 4.80 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 97 N/A n/a n/a 5.60 360 n/a n/a n/a n/a NO NRI YE eds Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI ___Single Element Head Supplemental Scan ICI 98 N/A n/a n/a 5.37 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head

____ N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI ___Single Element Head Supplemental Scan ICI 99 N/A n/a n/a 4.42 360 n/a n/a n/a n/a NO NRi YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan ICI 100 N/A n/a n/a 4.53 360 n/a n/a n/a n/a NO NRI YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 11 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 1: St. Lucie, Unit 2, RVHP Examination Summary SL2-16 Coverage Limitations Due to "A" "B"' Funnel Plug Weld V

> E 0 ID ID ID Qo o

.- 0 ý: Coverage Coverage Coverage m , 0

- S3: below below above - (.  :

0 2--Z weld on weld on weld on C" 'Sc downhill uphill uphill to side of side of side of Axial weld weld weld Angular Extent Extent Comments (in.) (in.) (in.) (deg.) Min Max Total (in.)

N/A n/a n/a 4.40 360 n/a n/a n/a n/a NO YES Needs Supp. Scan With Single Element Head N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI Single Element Head Supplemental Scan Vent 102 N/A n/a n/a 2.97 360 n/a n/a n/a n/a n/a NRI YES UT of bore performed N/A n/a n/a n/a 360 n/a n/a n/a n/a n/a NRI YES ET performed on J-Groove Weld NRI - No Recordable Indications IND - Indications

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 12 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 2: Coveracie Assessment for Nozzles Examined with Cnv~rz~na I imi$atinnc~

ID UT COVERAGE OD UT COVERAGE OD UT EXCLUSION ZONE "A" "B.. .C D"$ _....

ID ID Coverage Coverage shortage ID ID Axial below weld below weld Coverage Coverage OD height of Required on on below weld above weld Coverage IDOD ID/OD weld plug Coverage downhill downhill on uphill on uphill height Axial Axial Below exclusion side of side of side of side of Circ. ID from end Coverage Coverage Coy Funnel plug weld in 112" Nozzle # Weld weld weld weld weld Coverage of nozzle Overlap Gap Imperage Impacted exclusionzone (deg.) band (in.) (in.) (in.) In. (deg.) (in.) (in.) (in.)  ? Min Max Total (in.)

54 0.5 0.43 0.07 3.91 4.10 360 1.10 0.225 None Yes 144 :207 63 0.07 59 0.5 0.32 0.18 3.80 3.79 360 1.08 0.205 None Yes 169 229 60 0.18 66 0.5 0.44 0.06 4.08 3.68 360 1.10 0.225 None Yes 166- -220 54 0.06 70 0.5 0.43 0.07 4.68 4.80 360 1.13 0.255 None Yes 146. .207 .61 0.07 75 0.5 0.43 0.07 4.26 3.70 360 1.11 0.235 None Yes 157 1208 51 0.07 77 0.5 0.43 0.07 4.97 3.82 360 1.06 0.185 None Yes 138- -192 54,--- 0.07 79 0.5 0.43 0.07 4.68 3.40 360 1.04 0.165 None Yes -17. -211 `94 0.07 80 0.5 0.44 0.06 4.80 3.50 360 1.05 0.175 None Yes 161 220 - 0.06 81 0.5 0.48 0.02 4.62 3.30 360 1.18 0.305 None Yes 150 208 58 0.02 83 0.5 0.43 0.07 4.91 3.14 360 1.06 0.185 None Yes 156 212 56 0.07 85 0.5 0.45 0.05 4.97 3.58 360 1.19 0.315 None Yes 139 197 58 0.05 86 0.5 0.40 0.10 4.86 3.19 360 1.10 0.225 None Yes 151 206 55 0.10 87 0.5 0.34 0.16 4.91 3.10 360 1.03 0.155 None Yes 149 200 51 0.16 88 0.5 0.32 0.18 5.80 3.00 360 0.98 0.105 None Yes 145 209 64 0.18 89 0.5 0.20 0.30 5.62 2.56 360 0.75 -0.125 0.125 Yes 135 188 53 0.30 90 0.5 0.49 0.01 6.33 3.34 360 1.20 0.325 None Yes 159 213 54 0.01 91 0.5 0.32 0.18 5.51 3.28 360 1.10 0.225 None Yes 169 223 ..54 0.18

St. Lucie Unit 2 L-2006-152 Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 13 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 TABLE 2: Coverage Assessment for Nozzles Examined with Coverage Limitations Note: Nozzle 79 coverage is limited for 94 degrees in the area of the funnel plug weld due to a mechanical restriction and the funnel plug weld itself that prevents the OD UT tooling from scanning this location. The limitation is due to localized deformation of the funnel that was caused by repair activities of adjacent nozzle 59 during the last refueling outage. The incident that caused the funnel deformation is documented in FPL condition report #2005-2263. Because of this restriction a PT examination was performed on the affected area starting on a plane located approximately 1/16" inch below the low hill J-groove weld toe and progressing to the end of the nozzle. The PT results were free of recordable indications.

Note: Nozzle 89 coverage is limited for 66 degrees centered at the low hill side starting at a position measured 0.2 inches below the downhill toe of the weld and extending for a distance of 0.125" toward the end of the nozzle. The limitation is due an unusually large fillet radius at the low hill side of the nozzle that restricts the OD UT probe travel and prevents the OD UT from obtaining complete coverage in this area. A limitation also exists at the site of the funnel plug weld for the dimensions listed in the table. Because of these restrictions a PT examination was performed on the entire nozzle circumference starting on a plane located approximately 1/16" inch below the low hill J-groove weld toe and progressing to the end of the nozzle. The PT results were free of recordable indications.

Note: The angular coordinate for the OD UT was established visually by placing the transducer module at the uphill side and declaring that position 180 degrees.

Position accuracy is estimated to be + - 20 degrees.

St. Lucie Unit 2 L-2006-152 a Docket No. 50-389 Attachment NRC Order EA-03-009 - Reactor Vessel Head and Page 14 of 14 Vessel Head Penetration Nozzle Inspection Results SL2-16 ID UT Coverage Below Weld at r 40.5" Coverage -

Down-hill Side Commitment End of

. Nozzle Figure 1: St. Lucie 2 CEDM Examination Coverage Parameters