ML17228B125
| ML17228B125 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/04/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17228B124 | List: |
| References | |
| NUDOCS 9505090245 | |
| Download: ML17228B125 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAF Y EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF T SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN ND ASSOCIAT RE UESTS FOR RELIEF FOR FLORIDA POWER AND LIGHT COMPANY ST.
LUCIE NUCLEAR PLANT UNIT 2 DOCKET NUMBER:
50-389
- 1. 0 INTRODUCTION The Technical Specifications for St. Lucie Nuclear Plant, Unit 2, state that the inservice inspection of the American Society of Mechanical Engineers (ASME) Code Class 1, 2,'nd 3 components shall be performed in accordance with Section XI of the ASME;Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
As stated in 10 CFR 50.55a(a)(3),
alternatives to the requirements of paragraph (g) may be
- used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4),
ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME
- Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"
to the extent practical within the ]imitations of design,
- geometry, and materials of construction of the components.
The regulations require that inservice examination of components and system pressure tests conducted during the first ten-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporatedlby reference in 10 CFR 50.55a(b) on the date twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein.
The applicable edition of Section XI of the ASME,Code for the St. Lucie Nuclear Plant, Unit 2, second 10-year inservice inspection (ISI) interval is the 1989 Edition.
The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Commission approval.
9505090245 950504 PDR ADOCK 05000389 PDR I
Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI of the ASHE Code is not practical for its facility, -information shall be submitted to the Commission in support of that determination and a request made for relief from the ASHE Code requirement.
After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i),
the Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger life, property, or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
In a letter dated August 4, 1993, Florida Power and Light Company submitted to the NRC its Second Ten-Year Interval Inservice Inspection Program Plan, Revision 0 and associated Requests for Relief for the St. Lucie Nuclear Plant, Unit 2.
Additional information was provided by the licensee in its [[letter::L-94-212, Frowards Rev 1 to JNS-PSL-204, Second Ten-Yr ISI Interval IST Program for Pumps & Valves,St Lucie Nuclear Power Plant Unit 2. Response to Open Items Noted in 930823 SE of IST Program Also Encl|letter dated August 22, 1994]].
2.0 EVALUATION AND CONCLUSIONS The staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has evaluated the information provided by the licensee in support of its Second Ten-Year Interval, Inservice Inspection (ISI)
Program Plan, Revision 0, and associated Requests for Relief for St. Lucie Nuclear Plant, Unit 2.,
Based on the information submitted, the staff adopts the contractor's conclusions and recommendations presented in the Technical Evaluation Report attached with the exception of Requests for Relief Nos.
RR-14 and RR-15.
The licensee has committed to provide additional information regarding Request for Relief No.
RR-14.
Request for Relief No.
RR-14 will be evaluated in a separate report.
With respect to RR-15, the contractor's TER recommends authorization of the licensee's proposed alternative on the basis of a proposed ultrasonic technique that was qualified at Turkey Point Plant, Units 3 and 4, on a weld mock-up calibration block which contained implanted cracks.
For the staff to authorize the licensee's alternative of performing an inside surface ultrasonic examination in lieu of an outside surface examination, the ultrasonic technique should be capable of detecting and sizing circumferentially and axially oriented surface-connected flaws such that no flaw accepted for continued service could exceed the Code-allowable crack dimension before the next scheduled examination.
NRC approval of a demonstration is not required, but the demonstration may be subject to inspection.
Request for Relief No.
RR-1 deals with examination requirements of reactor pressure vessel (RPV) welds including Examination Category B-A, Item Bl. 10 (which includes Items Bl. 11 and Bl. 12) that is the subject of augmented rules contained in 10 CFR 50.55a(g)(6)(ii)(A).
Alternatives to the augmented RPV inspections proposed for St. Lucie, Unit 2, are evaluated in separate correspondence.
Based on the contractor's review of the subject ISI program, no deviations from regulatory requirements or commitments were identified in the St. Lucie Nuclear Plant, Unit 2, Second Ten-Year Interval ISI Program Plan, Revision 0.
Requests for Relief Nos.
RR-1, RR-3, RR-5, RR-6, RR-8, RR-9, and RR-10 are granted pursuant to 10 CFR 50.55a(g)(6)(i).
The alternatives contained in Request for Relief No.
RR-4 (Parts 1 and 2),
13, and 15 (with provisions as stated above) are authorized pursuant to 10 CFR 50.55a(a)(3)(i).
The alternative contained in Request for Relief No.
RR-17 is authorized pursuant to 10 CFR 50.55a(a)(3)(i) provided that the required examinations are completed within the same period in which the proceeding examinations were performed, or earlier, so that there is not more than ten years between examinations.
Request for Relief No.
RR-16 is denied for reasons explained in the Technical Evaluation Report.
A summary of the relief requests is contained in the attached Table.
Principal Contributor:
C. K. Battige Date:
May 4, 1995
ST.
LUCIE NUCLEAR PLANT, UNIT 2 Second 10-Year ISI Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS
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- <',Vol'~:,'or.':Areato< be'xamined",";~;:";.;.
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- Licensee,Pr'oposed;'Alt'em'at(j'e';y,,'".Status'.-4'-'9 RR-1 Reactor Pressure Vessel B-A 81.11 Louer Shell to Intermediate Shell Circunferentiai Meld 101-171 Volunetric 1)
Periodic System Pressure tests per category B-P, Table IMB-2500-1 Granted 81.12 Shell Longitudinal Melds 101-124C(
101-122A 81.21 Dome Meld 102-101 2)
Inservice Hydrostatic tests.per Table IN-2500-1 81 ~ 22 Bottem Head Peel Segments 101-154A, 101-1548, 101-154C, 101-154D, 101-154E, 101-154F 3)
Conduct Nechani zed Ultrasonic Examinations to the extent practical.
8'1.30 Upper Shell-to-Flange
'Meld 101-121 81.40 Flange-to-Torus Meld 101-101 4) 50/70'i-modal ultrasonic examination of the inner 25 percent 8 D 83.90
~
Nozzle to Shell Melds 105-121a, 103-1218 RR-3 Pressurizer 8-D 83.110 Nozzle-to-Vessel Melds 103-60'I, 108-601-A, 108-601-8, 108-601-C, 108-601-D, 105-651 Volunetric 1)
Periodic System Pressure tests.
2)
Conduct UT Exams the extent practical.
Granted RR-4 Class 1 Piping (Part 1)
Systems 8 J 89.12 89.22 Longitudinal Seam Maids Voiwetric and/or Surface Examine longitudinal ueid only Authorized at intersection of circunferential Meld
ST.
LUCIE NUCLEAR PLANT, UNIT 2 Second 10-Year ISI Interval TABLE 1 SUNNRY OF RELIEF REQUESTS
,:;Relief,.;:
- ,Request
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.:>%".X>::<<';.;,";,<<gN>.>>..>?>..:j<<>Ilo.",?,!';:,'.,:.-'::,::;,Yotia,'"::or-.",'Arei'::to',be':.:'Examined L'icensae" Propo'sed Atterriitfve,':
',,,':...-';Status",.
RR-4 Class 2 Piping (Part 2)
Systems Maids C-F-1 C-F-2 C5;12, C5.22, C5.42 C5.52 C5.62 C5.82 Longitudinal Seam Melds Volunetric.
and/or Surface Examine longitudinal weld only at intersection of circunferential.weld Authorized RR-5 RR-6 Class 1 Reactor Coolant System Class 1 Piping Systems 8-J 8-F 8-J 89.11 85.130 89.11 Piping Dissimilar Hetal Melds RC-115-4, RC-115-1501-771-Ag RC-115-701-771, RC-115-1501-771 8,
RC.121-5, RC-112-1501-771-C, RC-124-1501-771-D, RC-124-1301-771, Piping Melds RC-123-201-258, RC-115-1, RC-115-401-258-8, RC-112-401-258-A, RC-151-FM-1, SI-148-FM-5, SI-148-FM-1, SI-149-FM-4, SI-149-FM-1, S I-150- FM 4, S I-151-FM-4>
SI-151-FM-1I SI-518-FM-1 Surface and Vo (unct r ic Volunetric and Surface 1) 100X surface exam 2)
UT exam to the maximm extent possible.
3)
Periodic system pressure tests.
1) 100X surface exam 2)
UT exam to the maxiaxm extent possible.
3)
Periodic system pressure tests.
Granted Granted 89.12 RC-115-109-722-LS-A, RC-115-103-722-LS-A, RC-115-103-722-A(
B9.31 RC-123-205-771 RR-8 Shutdown Cooling Heat Exchanger C-A C1.10 Flange to Body Meld (1-2701)
Body to Tubesheet Meld (1-2702)
Voluaetric 1)
UT exan to the maxisua extent practical 2)
System pressure test Granted
ST.
LUCIE NUCLEAR PLANT, UNIT 2 Second 10-Year ISI Interval
. TABLE 1 SUNNRY OF RELIEF REQUESTS
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0'":I tens,'".',:::
No'k."'.,:-'::.:"-"'Vol~':',or,.':'.Arei;to';be Kiuained;'.;:;:.',.:',::.."::Nethod
',:":".'; ~'.I kcensee.,Pr'opoa'o'dAller'natfm..':
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RR-9 RR-10 Steam Generator C-B Class 2 Piping C-F-1 C-F-2 C2.21 C5.11 C5.12 C5.81 Steam Nozzle to Heed Meld (SG-2A-105-201)
- Fee&ster Nozzle to Shell Meld (SG-2A-111-221)
HS-I-FM-I-LS, SI-146-FM-2, S1-110-FM-1, HS.33.FM-1-LS, SI-110-8-SM-1, SI-213-FM-2, Sl-213-FM-1 Surface and Volunetric Volunctric and/or Surface 1)
System pressure test 2)
Perform to the extent practical the volunetric and surface exams 1)
System pressure tests 2)
Voluaetric and surface exam to the extent practical Granted
~Relief Not Required Granted RR-13 RR-14 RR-15 RR-16 RR-17 Ultrasonic Calibration Blocks Reactor Pressure
- Vessel, Steam Generator, Pressurizer Class 1 Piping System NIS-1 and NIS-2 form Subnittal Reactor Pressure Vessel Appendix
- 111, 111-3400 IN-2412 IN-2420 IMC-2412 IMC-2420 B-J IMA.6620 8-D NA NA 89.11 NA 83.90 83.100 Existing Ultrasonic Calibration Blocks Scheduling of examinations per Inspection Program 8
Nozzle-to-Pipe Melds 401-128-A, RC-114-1, 201-128A, RC-112-6, 201-128-BI RC-121-6, 401-128-BI RC-123-1, 201-128-C, RC-124-6, 201-128-D, RC-115.6 Ower's Report for Inservice Inspections and submittal of the 90-Day Suanary Report Scheduling requirements for RPV nozzle-to-vessel uelds 8 Reactor pressure vessel nozzle inside radius HA Voiunet ric and/or Surface Voiunetr Ic and Surface NA Vol unct ri c Use existing ultrasonic calibration block design Reschedule examinations for the reactor pressure
- vessel, steam generator, and pressurizer to be exanined within one specified period 1)
UT examination of the O.DE of the veld remotely from inside the pipe 2)
System Pressure Test Submit FPBL docunents 100X volunetric -examination during the second period Authorized
'Mill be evaluated in separate report Authorized Cond>tionaily Denied Authorized Conditionally