ML20236T288
| ML20236T288 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/16/1998 |
| From: | Thomas K NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-M95204, NUDOCS 9807280081 | |
| Download: ML20236T288 (26) | |
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W E: & f42 p $ UNITED STATES g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30066-4001
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July 16,1998 l ,
LICENSEE: Union Electric Company FACILITY: Callaway Plant, Unit 1
SUBJECT:
MEETING WITH UNION ELECTRIC COMPANY REGARDING THE l PROPOSED AMENDMENT TO THE TECHNICAL SPECIFICATIONS TO ALLOW THE INSTALLATION OF ELECTROSLEEVES IN THE STEAM GENERATORS AT THE CALLAWAY PLANT, UNIT 1 (TAC NO. M95204)
On Wednesday, July 7,1998, a meeting was held between Union Electric Company (UE) and !
the NRC to discuss the status of the NRC's review of UE's proposed technical specification amendment to allow the installation of electrosleeves in the Callaway Plant steam generators.
Attachment 1 is a list of attendees. Attachment 2 is the licensee's presentation material used during the meeting. j l
In a May 20,1998 letter to UE, in which the staff discussed concems regarding UE's responsiveness to requests for information pertaining to the review, the staff indicated it was ;
interested in meeting with UE to understand UE's plans relative to the electrosfeeving i amendment, including UE's views of the alternatives discussed in the letter. The staff has determined that to date, UE has not provided the technical basis required to approve the use of !
the electrosteeve technology, primarily due to problems of inspectability of the reactor coolant pressure boundary once the sleeves are insto :ed. Representatives from Framatome d Technologies, the developer of the efectrosfeeve process, and representatives from TVA (Sequoyah) and Duquesne Light Iaaver Valley) were also present and participated in the ,
meeting. Duquesne Light has rsansted approval to install electrosleeves in the Beaver Valley l steam generators and is working with UE and Framatome Technologies in addressing the staff's questions on this new technology.
UE indicated that it, as well as Duquesne Light, planned to pursue an altemative amendment l that would limit the period of time electrosteeves would be installed and in service to two operating cycles while the issue of inspectability is being resolved. In addition to providing a supplement to the proposed amendment, specifically requesting the limited use of the electrosleeves, UE and Duquesne Light indicated that they will submit an updated topical report, which will fully respond to the staff's questions applicable to a two cycie amendment and
- include a risk assessment for a two cycle amendment. In addition, UE will provide an analysis of the root cause(s) of the quality assurance issues contained in the submittals provided to the l
staff for review, and the corrective actions taken to prevent recurrence. UE will include in the analysis, summaries of (1) the reports from the audits performed at Fran"uome Technologies, (2) UE and Framatome Technologies procedures that permitted the problems to occur, and (3) a revised or new procedure that will prevent recurrence. Duquesne Light will also respond to the quality assurance issues as they apply to Framatome Technologies. UE and Duquesne Light indicated that the above information will be submitted to the staff for review by August 31,
' 1998.
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To date, the Callaway Plant has been the lead plant pursuing approval for the installation of electrosleeves, with installation planned for Fall 1999. However, Duquesne Light indicated they would like to install electrosleeves in the Beaver Valley Unit 2 steam generators _ in early 1999.
The utilities will notify the staff in the near future if a change in the lead plant is made.
At the conclusion of the meeting, Framatome Technologies presented a summary of its effort in pursuing techniques for inspection of the reactor coolant pressure boundary following installation of electrosleeves.
Original Signed By Kristine M. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-482 Attachments: 1. List of Meeting Attendees
- 2. Meeting Presentation Material
- cc w/atts: See next paga
- i. DISTRIBUTION: (Hard Coov)
Docket -
PUBLIC PDIV-2 Reading KThomas OGC ACRS
, DISTRIBUTION: (E-Mail)
SCollins/FMiraglia BBoger EAdensam WBateman
. EPeyton TMartin (SLM3)
RSmith DBrinkman ADromerick FLyon TSullivan GHomseth CBeardslee . DJackson BSheron MMcNeil EMurphy LLund PRush RHeman
' DOCUMENT NAME: CAL 95204.MTS .
To receive a copy of this document, indicate in the box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy OFFICE . PM/PDIV-2 LA/PDIV-2 NAME KThomat6fY\ L EPeyton=" o f "
DATE- 07X@8 07AS8 OFFICIAL RECORD COPY i
. \
To date, the Callaway Plant has been the lead plant pursuing approval for the installation of electrosleeves with installation planned for Fall 1999. However, Duquesne Light indicated they would like to install electrosleeves in the Beaver Valley Unit 2 steam generators in early 1999.
The utilities will notify the staff in the near future if a change in the lead plant is made.
At the conclusion of the meeting, Framatome Technologies presented a summary of its effort in pursuing techniques for inspection of the reactor coolant pressure boundary following installation of electrosleeves.
Kristine M. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects ill/lV Office of Nuclear Reactor Regulation Docket No. 50-482 Attachments: 1. List of Meeting Attendees i
- 2. Meeting Presentation Material ,
cc w/atts: See next page l
l l
l l
3-cc w/ encl:
Professional Nuclear Mr. Otto L. Maynard Consulting, Inc. President and Chief Executive Officer 19041 Raines Drive Wolf Creek Nuclear Operating Corporation Derwood, Maryland 20855 Post Office Box 411 Burlington, Kansas 66839 John O'Neill, Esq.
l Shaw, Pittman, Potts & Trowbridge Mr. Dan 1. Bolef, President 2300 N. Street, N.W. Kay Drey, Representative Washington, D.C. 20037 Board of Directors Coalition i for the Environment Mr. H. D. Bono 6267 Delmar Boulevard Supervising Engineer University City, Missouri 63130 '
Quality Assurance Regulatory Support Union Electric Company Mr. Lee Fritz Post Office Box 620 Presiding Commissioner Fulton, Missouri 65251 Callaway County Court House 10 East Fifth Street
- U.S. Nuclear Regulatory Commission Fulton, Missouri 65151 Resident inspector Office l 8201 NRC Road .
Mr. Alan C. Passwater, Manager Steedman, Missouri 65077-1302 Licensing and Fuels Union Electric Company ,
Mr. J. V. Laux, Manager Post Office Box 66149 Quality Assurance St. Louis, Missouri 63166-6149 Union Electric Company Post Office Box 620 Mr. Garry L. Randolph Fulton, Missouri 65251 Vice President and Chief Nuclear Officer Union Electric Company Manager- Electric Department Post Office Box 620 Missouri Pub!ic Service Commission Fulton, Missouri 65251 301 W. High Post Office Box 360 Jefferson City, Missouri 65102 i Regional Administrator, Region IV U.S. Nuclear Regulatory Commission l Harris Tower & Pavilion l 611 Ryan Plaza Drive, Suite 400 )
Arlington, Texas 76011-8064 Mr. Ronald A. Kucera, Deputy Director Department of Natural Resources l P.O. Box 176 Jefferson City, Missouri 65102-I-
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MEETING WITH UNION ELECTRIC COMPANY LIST OF MEETING ATTENDEES July 7,1998 Union Electric Comoany g E. Kahl K. Thomas l D. Shafer R. Smith j T. Herrmann D. Brinkman J A. Dromerick Framatome Technoloales F. Lyon T. Fullivan J. Helmey G. Homseth J. Galford C. Beardslee J. Fleck D. Jackson C. England B. Sheron R. Edwards W. Bateman M. McNeil l ABB-Combustion Engineering L. Lund E. Murphy L. Collins P. Rush )
R. Heman Southem Califomia Edison J. Fox McGraw-Hill L
D. Stelfox Argonne National I shoratorV B. Shack Duquesne Light l l
G. Kammerdeiner l
Tennessee Vallev Authority D. Goetchens ii. Cothron Attachment 1 o
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. SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4
- Accentance criteria
- a. As used in this specification:
- 1) Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections;
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- 2) Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube;
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- 3) Dearaded Tube means a tube containing imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation;
- 4) % Degradation means the percentage of the tube wall thickness affected or removed by degradation;
- 5) Defect means an imperfection of such severity that it exceeds '
the p' ugging or repair limit. A tube or sleeve containing a
, defect is defective; l
- 6) Pluacino or Reoair Limit means the imperfection depth at or beyond which the tube shall be removed from servict by plugging or repaired by sleeving and is equal to 40% of the n.ainal tube wall thickness. The plugging limit for laser welded sleeves is equal to 39% of the nominal sleeve wall thickness)(,
- 7) Unserviceable describes the condition of a tub f it leaks or contains a defect large enough to affect its ructural integrity in the event of an Operating Bas Earthquake, a loss-of-coolant accident, or a steam line or edwater line break as specified in Specification 4.4.5.3c., o -
' 8) Tube insoection means an inspection of steam generator tube from the point of entry (hot leg completely around the U-bend to the top support o cold leg. For a tube repaired by sleeving, the tube ection shall include the sleeved portion of the t ,
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- f /bf th ) l/ r. / h / %re d o rl* w re.r is e g 16 2o 2' of H= runn.1 riewm .ssit +Aic.x s
CALLAWAY - UNIT 1 3/4 4-14' Amendment No. 116 (correction)
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'.i SURVEILLANCE RE0VIREMENTS (Continued) 9)
Preservice InsnectM D means an inspection of the full length of each tube in each steam generator performed by addy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be perfomed prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections; and
- 10) Tube Renair refers to a process that reestablishes tube serviceability. Acceptable tube repairs will be perfomed by the following processes:
a) Laser welded sleeving as described in Westinghouse Technical Report WCAP-14596-P, " Laser Welded Elevated Tube Sheet Sleeves for Westinghouse Model F Steam Generators."
O#A March 1996(Proprietary)
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- b. The steam' generator shall be detemined.0PERABLE after completing the corresponding actions (plug or repair by sleeving all tubes exceeding the plugging or repair limit and all . tubes containing through-wall cracks) required by Tables 4.4-2 and 4.4-3.
4.4.5.5 Reports
- a. Within 15 days following the completion of each inservice inspection j
p s,
of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the Comission in a Special Report pursuant to Specification 6.9.2;
- b. The complete results of the steam generator tube inservice inspection shall be submitted to the Comission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:
- 1) Number and extent of tubes and sleeves inspected, I
- 2) Location and-percent of wall-thickness penetration for each t
indication of an imperfection, and l 3) Identification of tubes plugged or repaired. l
- c. Results of steam generator tube inspections, which fall into Category C-3, sha1! be reported in a Special Report to the Comission pursuant to Specification 6.9.2 within 30 days and prior to resumption of plant operation. This report shall provide a description of investigations conducted to detemine cause of the tube degradation and corrective measures taken to prevent recurrence.
G CALLAWAY - UNIT 1 3/4.4-15 Amendment No. 116 3 .
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INSERT A TO TS 4.4.5.4.a.10 (Page 3/4 4-19
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b) Electrosleeving as described in Framatome Technical Report BAW-10219P, Revision 2, "Electrosleeving Qualification for PWR Recirculating Steam Generator Tube Repair." Any steam generator tube containing an Electrosleeve !
which has been inservice for 2 cycles of plant operation must be removed from service.
i INSERT B TO TS BASES 3/4.4.5 (Pare B 3/4 4-3)
The plugging or repair limit for the pressure boundary portion of Electrosleeves is determined to be 20% through wall of the nominal sleeve wall thickness (as determined by NDE).
1 I
C _. ..._____._______-____ _ __ -
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TABLE 4.4 3 STEAM GENERATOR REPA1 RED TUBE INSPECTION 2ND SAMPLE INSPECflON 1ST SAMPLE INSPECTION Acten Recuwed Acten Reevired Result Samow See Resus None NA. N.A.
A mewnum of 20% of C.1 repowed tubes (1)(2)
- C.1 None C2 Plur 6efective repsired tubes end inspect 100% of the repaired tubes in this S.G.
C-2 rium derecieve reeswed tutws C3 Pefferm acten for C 3 tout of first somete AI ether S.G.s are None C.3 inspect el repolted tubes in this .,
S.0 plug eefective tutes and C1 A-
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' hspect 20% of the repelred tubes in each other S.G.
Notifestion to NRC pursuerd to Some S.G.s C 2 Perform ection for C 2 resut of first semple 150.72 (b)(2) of 10 CFR Port 50 but no additional S.G. are C 3 Additionet S.G. is inspect se repelred tubes b each S.G. and plug defective C-3 tubes. Notifcetionle NRC a pursuantle150.72 (t)(2)of 10
, A CFR Port 50 ee cope nson.
. (1) Each eepen method is sensalered e seperate populaten for setermes r s based oneutage piens.
(2) Tee inpection of repaired tules sney be perfoerned on lutes trem t 4 si m gener .
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- ..v Amendment No.116 j CALLAWAY - UNIT 1 3/44-17a
BASES STEAM GENERATORS (Continued)
The plugging or repair limit for the pressure boundary portion of laser welded sleeves is determined to be 39% through-wall (by NDE). The laser welded sleeve repair limit applicable to the pressure boundary portion of the sleeve is established in WCAP-14596. Appropriate NDE techniques are also I # # discussed in WCAP-14596.
5 MsW8 Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to Specification 6.9.2 prior to resumption of plant operation. Such cases will be considered by the commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional addy-current inspection, and revision of the Technical Specifications, if necessary.
3/4.4.6 REACTOR C0OLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS Leakage Detection Systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure J boundary. These Detection Systems are consistent with the recommendations of i 1
Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.
3 /4. 4. 6. 2 OPERATIONAL LEAKAGE PRESSURE BOUNDARY LEAXAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. I l
Therefore, the presente of any PRESSURE BOUNDARY LEAXAGE requires the unit to be promptly placed in COLD SHUTDOWN. l Industry experience has shown that while a limited amount of leakage is
(~ expected from the RCS, the unidentified portion of this leakage can be reduced .
to a threshold value of less than 1 gpm. .This threshold value is sufficiently l low to ensure early detection of additional leakage. l l
The total steam generator tube leakt.ge limit of 600 gpd for all steam l l
generators not isolated from the RCS ensures that the dosage contribution from i I the tubeleakage will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of either a steam generator tube rupture or l
steam line break. The 600 gpd limit is conservative compared to the
( assumptions used in the analysis of these accidents. The 150 gpd leakage limit per steam generator ensures that steam generator tube integrity is ,
maintained in the event of a main steam line rupture or under LOCA conditions.
The 10 gpm IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAXAGE by the Leakage Detection Systems.
The CONTROLLED LEAKAGE limitation restricts operation when the total flow from the reactor coolant pump seals exceeds 8 gpm per RC pump at a nominal RCS pressure of 2235 psig. This limitation ensures adequate
.- performance of the RC pump seals.
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83/44-4 Amendment No.116 CALLAWAY - UNIT 1
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