ML17311A801

Forwards Palo Verde Nuclear Generating Station Unit 3 SG Eddy Current Exam Fourth Refueling Outage.

ML17311A801
Person / Time
Site:	Palo Verde
Issue date:	03/31/1995
From:	James M. Levine ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17311A802	List: ML17311A801
References
192-00927-JML-B, 192-927-JML-B, NUDOCS 9504180142
Download: ML17311A801 (32)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9504180142 DOC.DATE: 95/03/31 NOTARIZED: NO DOCKET FACIL:STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH. NAME LEVINE,J.M.

RECIP.NAME

SUBJECT:

Forwards Eddy AUTHOR AFFILIATION Arizona Public Service Co. (formerly Arizona Nuclear Power RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

"Palo Verde Nuclear Generating Station Unit Current Exam Fourth Refueling Outage."

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DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR TITLE: OR Submittal: Inservice/Testing/Relief from 1 ENCL / SIZE:

ASME Code 2 +~

GL-89-04 0 NOTES:Standardized plant. 05000530 RECIPIENT COPIES RECIPIENT COPIES ID LTTR ENCL ID CODE/NAME LTTR ENCL

'1 PD4-2 PD CODE/NAME'D4-2 LA 1 1 1 TRAN,L 1 1 INTERNAL: 6 6 AEOD/SPD/RAB 1 . 1 Y E -ER 01 1 1 NRR/DE/EMCB 1 1 NRR/DE/EMEB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 RES/DSIR/EIB 1 1 EXTERNAL: LITCO BROWN, B 1 1 LITCO RANSOME,C 1 1 NOAC 1 1 NRC PDR 1 1 D

u NOTE TO ALL'RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P!-37 (EXT. 504-2083 ) TO ELI!iIINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 19

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Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 192-00927-JML/BAG/KR JAMES M. LEVINE March 31, 1995 VICE PRESIDENT NUCLEAR PRODUCTION U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 3 Docket No. STN 50-530 (License No. NPF-74)

Special Report 3-SR-94-001-01 Attached please find Supplement 1 to Special Report 3-SR-94-001 prepared and submitted pursuant to Technical Specification (TS) Surveillance Requirement 4.4.4.5.b and TS 6.9.2. This supplement is being submitted to provide the complete results of the Steam Generator Tube Inservice Inspection.

A copy of this supplement is being forwarded to the Regional Administrator, NRC Region IV. If you have any questions, please contact Burton A. Grabo, Supervisor, Nuclear Regulatory Affairs, at (602) 393-6492.

Sincerely, JMUBAG/KR/rv Attachment cc: L. J. Callan (all with attachment)

K. E. Perkins K. E. Johnston

". nor qg 9504180142 'TI50331 PDR ADOCK 05000530

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NRC Document Control Desk Special Report 3-SR-94-001-01 Page 2 bcc: W. E. Ide Source Document File CRDR File: ~NA RCTS File: 041724 D. F. Garchow 7565 R. E. Younger (OSRC) 7997 A. C. Rogers 1534 R. G. Hogstrom 7545 N. Meador 7636 D. Brevig D. Cox R. F. Schaller 7696 J. H. Thompson 7602 Responsible Department (required review):

T. C. Cannon 7545

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Distri53.txt Distribution Sheet Priority: Normal From: Elaine Walker.

Action Recipients: Copies:

M Fields Not Found C Jamerson Not Found Internal Recipients:

RES/DET/MEB Not Found RES/DET/ERAB Not Found OGC/RP Not Found FILE CENT.ER,.01~ Not Found ACRS Not Found External Recipients:

NOAC Not Found INEEL Marshall Not Found Total Copies:

Item: ADAMS Package Library: ML ADAMS"HQNTAD01 ID'03676988

Subject:

OR Submittal: Inseryice/Testing/Relief from ASME Code Body:

Docket: 05000530, Notes: Standardized plant.

Page 1

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David Mauldin 10CFR50.55a Vice President Mail Station 7605 Palo Verde Nuclear f Nuclear ngineering TfL (623) 393-5553 P.O. Box 52034 Phoenix, AZ 85072-2034 Generating Station and Support FAX (623) 393%077 102-04395-CD M/SAB/RKB January 12, 2000 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001

References:

1. APS Letter No. 102-04232-WEI/AKK/MLG, dated January 11, 1999, from W.E. Ide, APS, to NRC, "Unit 3 First Ten Year Inservice Inspection Program Revision."

2. APS Letter No. 102-04312-WEI/SAB/RKB, dated July 16, 1999, from W.E. Ide, APS, to NRC, "Unit 1 First 10-Year Interval Inservice Inspection (ISI) Program Revision 2."

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 3 Docket No. STN 50-530 First 10-Year Interval Inservice Inspection Programs Revision 3 In reference 1 above, pursuant to the requirements of 10 CFR 50.55a(g)(4) and 10 CFR 50.55a(g)(5)(i), Arizona Public Service Company (APS) submitted revision 2 to the PVNGS Unit 3 first 10-year interval Inservice Inspection (ISI) program. The revision documented the final status of the PVNGS Unit 3 first interval ISI program and was accompanied by several new or revised requests for relief.

In preparation of the final revision of the Unit 1 first 10-year ISI program, reference 2, APS identified minor changes to the Unit 3 first interval ISI program which were not included in the revision 2 submittal. Those changes are provided in enclosure 1.

In addition, APS identified the need for an additional request for relief that was not included in the original Unit 3, revision 2 submittal. Pursuant to the requirements of 10 CFR 50.55a(g)(5)(iv), APS hereby submits Relief Request No. 15 for the Unit 3 first interval ISI program. This relief request is identical to Relief Request No. 16 for the Unit 1 first interval ISI Program submitted in reference 2, above.

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U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Units 3 First Interval ISI Program - Revision 3 Page 2 Relief Request No. 15, provided in enclosure 2, requests relief from the IWB-5210 and Table IWB-2500-1 requirements to perform VT-2 examinations of the reactor vessel at no less than normal operating pressure. This examination is impractical due to extreme temperatures and high radiation fields in certain areas requiring personnel occupancy in order to complete the exam.

No commitments are being made to the NRC by this letter.

Should you have any questions, please contact Scott A. Bauer at (623) 393-5978.

Sincerely, CD M/SAB/RKB/kg Enclosures cc: E. W. Merschoff [Region IV Administrator]

M. B. Fields [NRR Project Manager]

J. H. Moorman [Sr. Resident Inspector]

1 ENCLOSURE 1 ASME SECTION XI F.I RST 10 YEAR INTERVAL ISI PROGRAM REVISION 3 FOR PALO VERDE NUCLEAR GENERATING STATION UNIT 3

INSERVICE INSPECTIONAL PROGRAM

SUMMARY

MANUAL PALO VERDE NUCLEAR GENERATING STATION UNIT 3 ARIZONA PUBLIC SERVICE COMPANY PVNGS P.O. Box 52034 5801 S. Wintersburg Road Phoenix, AZ 85072-2034 Wintersburg,Az 85354-7529 PREPARED BY: l-S , ~/8-? '?

PREPARED BY: DATE: /

'ATE:

REVIEWED BY:

ANIl CONCURRENCE: DATE:

APPROVAL BY ENGINEERING DEPARTMENT LEADER: DATE: +l i COMMERCIAL PROGRAM NO: ISI-3 SERVICE DATE: 01/08/88 REVISION NO: 3 DATE: 9-15-99

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EUKXKEQH Cover 3.

ii'and iii 1-1 and 1-2 1-3 and 1-4 1-5 1-6 and 1-7 4-1 and 4-2 Table l-l page 1 of 2 1-1. page 2 of-. 2 1-2 page 1 and 2 of 2 1-3 page 1 of 2 1 3 page 2 of 2 1-4 1-5 page 1 of 2 1-5 page 2 of 2 1-6 page 1 of 3 1-6 page 2 and 3 of 3 1-7 page 1 of 4 1-7 page 2 thru 4 of 4 1-9 page 1 thru 3 of 5 1-9 page 4 and 5 of 5 1-10 1-12 page 1 of 2 1-12 page 2 of 2 1-13 1-14 1-15 1-16 1-IWF page 1 of 3 1-IWF page 2 and 3 of 3 1 1-RCP 0 REV. 3 9-15-99

~ t 5-1 and 5-2 Table 2-1 page 1 thru 2 of 3

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2-1 page 3 of 3 2-2 page 1 of 2 2 2-2 page 2 of 2 1 Table 2-3 page 1 of 4 1 2-3 page 2 and 3 of 4 2 2-3 page 4 of 4 0 2-4 2-5 page 1 thru 3 of 4 2-5 page 4 of 4 2-6 2-7 2-IWF page 1,3, and 4 of 6 2-IWF page 2,5, and 6 of 6 6-1 and 6-2 Table 3-1 page 1 of 2 3-1 page 2 of 2 3-IWF Table 2-AHE page 1 and 3 of 3 2-AHE page 2 of 3 Table 2-CFR page 1 and 2 of 6 2-CFR page 3 of 6 2-CFR page 4 thru 6 of 6 9-1 9-2 9-3 thru 9-7 9-8, 9-9 and 9-9A 9-10 9-11 thru 9-22 9-23 thru 9-25 10-1 10-2 11-1 thru 11-4 Zone Drawings (see Dwg)

REV. 3 9-15-99

3.3 The preservice examinations were performed with examination techniques, both automated and manual; similar to those planned for use during Znservice Inspection. The examination limitations noted during the preservice examinations were documented in requests for relief submitted with the preservice examination program. There have been no additional code limitations poted during the formulation of this program other than those contained in the Request for Relief Section.

All items that. are scheduled for examination will be examined to the extent practical. In addition, any code limitations that are noted during the examinations will be documented in the summary z'eports that are prepared after each outage.

3.4 The three types of examinations utilized to perform Inservice Inspections, along with the actual nondestructive examination technique, are identified in the legend below:

VT - Visual VT - 1 (General Condition)

VT - "2'Leakage)

VT - 3 (Structural Condition)

VT - 4 (Operability)

S Surface PT - Liquid Penetrant MT Magnetic Particle ET Eddy Current VOL - Volumetric UT Ultrasonic RT - Radiograohy All the above nondestructive examination techniques will be performed using specific techniques and procedures that are identified in ASME Section XI, or alternative examinations that are demonstrated to be equivalent or superior to those identified.

3.5 The Znservice Inspection Program was prepared in accordance with Program B of ASME Section XI. The initial 10 year inspection interval and corresponding inspection periods are defined below:

First Inspection Interval: 1-8-88 to 1-10-98*

Period One 1-8-88 to 5-10-91 Period Two 5-11-91 to 9-10-94 Period Three 9-11-94,to 1-10-98 These dates have been modified to a common interval start date for all three PVNGS units. This is in accordance with NRC letter dated October 21, 1987, from E.A. Licitra, NRC, to E.E. Van Brunt, 0'r.,ANpp, "Znservice Inspection Pro=

grams Palo Verde, Units 1, 2, and 3" to allow the three units to be under the same ASME Section XI edition and addenda. It should be noted that the intervals/periods may change between units to allow for extended outage dura-tions per IWA-2400 of ASME Section XZ. The Unit 3 interval has been increased by 9 months and 23 days due to the extended duration of the first re-fueling outage REV. 3 1-3 9-15-99

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" The first inspection interval has been extended 1 year to 1/10/99 as allowed by ZWA-2400(c).

3.6

,The examination categories of ASME Section XZ were utilized to develop this program for all systems, components, and supports. The Program summary tables contained in Sections 4.0 and 5.0 are organized by examination category for ASME Class 1 and 2 systems, respectively. For each examination category, these tables identify the system, line number, nondestructive examination method, total number of items, required examination amount for each inspection period, and running percentage. For ASME Class 3 systems, the examinations categories are identified in Section 6.0.

3.7 The evaluation of all examination results will be performed in accordance with ASME Section Xi Articles IWA and ZWB-3000.-in addition, all applicable repairs and replacements will be performed in accordance with ASME Section Xi Articles IWA, ZWB, ZWC, IWD, and ZWF-4000 and 7000. Pressure tests will be performed only on welded repairs or replacements, in accordance with IWA-4000 and 5000.

Both the evaluations and repair or replacement will be performed in accordance with the 1980 Edition through and including the Winter 1981 Addenda of ASME Section XZ, or,- later editions and addenda of ASME Section XI reference in 10 CFR 50.All repairs and replacements will be documentedin accordance with the Work Control program, and are maintained at Palo Verde for review.

3.8 System pressure tests will be performed in accordance with ASME Section Xi and as identified in Sections 4.0, 5.0, and 6.0 for ASME Class 1, 2, and 3, respectively. These tables also identify the type of pressure test, test frequency, any applicable requests for relief, and references the appropriate ASME Section XI Article for each of the ASME Code Classes.

3.9 Based on the PVNGS UFSAR, an augmented examination is required for protection against postulated pipe failures. This augmented examination program includes the following high energy piping systems located between the containment penetration and the main steam support structural wall:

Main Steam Feedwater Steam Generator Blowdown Downcomer Feedwater The summary tables in Section 7.0 identify each system, along with the required examination amounts and frequencies. As shown by. this table, a volumetric examination of all longitudinal and circumferential welds is scheduled. These welds will be examined to the maximum extent practical.

any limitations to the examination will be included and documented on the examination report prepared in accordance with ASME Section XI.

1-4 REV. 3 9-15-99

0 RELIEF REQUEST INDEX DESCRIPTION Hydraulic and Mechanical Snubbers will be tested in accordance with PVNGS Technical Specifications.

Withdrawn Insulation will not be removed for visual examinations or welded or mechanical attachments.

Level 111 Personnel will be recertified by examination every 5 years.

Withdrawn Withdrawn Class 2 and 3 Systems Pressure Test (revised)

Withdrawn Steam Generator Handhole Pressure Test Main Steam Nozzle Volumetric Examination Code Case N498-I Class 1 Pressure Test Boundary Reactor Vessel Shell and Head Coverage Misc. Code Limited Examinations Restricted Access Under Reactor Vessel For VT-2 Examination REV. 3 9-15-99

ENCLOSURE 2 ASME SECTION XI RELIEF REQUEST NO. 16 TO THE FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM FOR THE PALO VERDE NUCLEAR GENERATING STATION UNIT 3

Relief Request No. 15 Restricted Access under the Rx Vessel for VT-2 Exam Code Class Code Reference ASME Section XI, Division 1, 1980 Edition, Winter 1981 Addenda, IWB-5210 and Table IWB-2500-1 Examination Category B-P Item Numbers B15.10 and B15.11 Component Description Reactor Vessel PVNGS Unit Requirement IWB-5210 and Table IWB-2500-1 of ASME Section XI, require that the reactor vessel [Category B-P, Items B15.10 and B15.11] be VT-2 examined at a test pressure not less than the nominal operating pressure associated with 100 percent rated reactor power, to identify leakage.

Alternate PVNGS will conduct VT-2 examinations on all portions of the reactor Testing vessel, which are accessible during Mode 3 without endangering personnel from undue heat or radiation exposure.

However, in lieu of performing VT-2 visual exams in areas that are hazardous to personnel (i.e. under the reactor vessel), PVNGS will monitor for reactor vessel leakage using leak detection methods provided in the design of the plant.

Basis For Pursuant to 10 CFR 50.55a (g)(5)(iv), relief is requested on the basis Relief that conformance with the code requirement is impractical. Specifically, relief is requested from the requirement to visually inspect the entire reactor vessel while pressurized to the pressure associated with 100 percent rated reactor power based on design limitations which create personnel hazards in certain areas required to be examined.

The requirement to VT-2 examine the reactor vessel is to ensure that the vessel has been reassembled correctly and that no leakage is present. Because the walls of the reactor Vessel are essentially vertical, the code allows the examination to be limited to the lowest elevation where leakage will accumulate [IWA-5242(a)]. In addition the

Unit 3 First Interval ISI Program 0

Relief Request No. 15 (continued) code requires that the surrounding areas, including floor areas, be inspected for evidence of leakage [IWA-5242(b)].

PVNGS cannot comply with the code requirements to perform this inspection at Mode 3 because of high area temperatures and high radiation areas.

The exams require personnel to access areas where radiation fields are between 2 to 12 Rem/hour.

Accessing the bottom of the reactor vessel to assess accumulated leakage, while the system is depressurized, is physically possible.

However, PVNGS is constructed in such a way that reactor vessel leakage which would accumulate at the bottom of the insulation around the vessel or on the floor cannot be distinguished from leakage from other sources such as leakage from the pool seals.

While direct visual examination may detect gross leakage, more sensitive methods of detecting leakage from the reactor vessel are available, as discussed below, which do not endanger plant personnel.

Additional Reactor coolant system (RCS) pressure boundary leakage is monitored information by the control room staff in several different ways:

1. Monitoring of the space between the double 0-ring seal on the reactor vessel closure head.

2. Containment atmosphere particulate radioactivity monitoring.

3. Containment atmosphere gaseous radioactivity monitoring.

4. Containment relative humidity monitoring.

5. Containment sump level rate of change and discharge monitoring.

6. RCS water inventory balance measurements.

Technical Specification 3.4.14, RCS Operation Leakage, allows for only 1 gpm unidentified leakage and no pressure boundary leakage. The first four methods, above, provide continuous monitoring with alarms.

Sump levels are monitored every hour and the RCS water inventory balance is performed every three days. If greater than 1 gpm leakage is detected, the leakage must be reduced to within limits within four hours

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Relief Request No. 15 (continued) or be in Mode 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

PVNGS believes that the RCS leakage monitoring performed by the control room staff satisfies the requirement for detection of RCS pressure boundary leakage from the reactor vessel. Performing a VT-2 exam on the bottom of the reactor vessel would not provide better information than is possible by other means and does not warrant the risk of injury to plant personnel from extreme heat and high radiation exposure.

Approval Relief is requested in accordance with 10 CFR 50.55a (g)(5)(iv). This examination is impractical due to extreme temperatures and high radiation in certain areas requiring personnel occupancy in order to complete this exam.

References 1. ASME Section XI, Rules for Inspection and Testing of Components of Light Water Cooled Plants, 1980 Edition, Winter 1981 Addenda.

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