ML20132B593

Summary of 961106 Meeting W/B&Wog Re Proposals to Resolve Three Open Items in Staff 960913 Draft SE for B&Wog Generic License Renewal Program Topical Rept BAW-2244, Demonstration of Mgt Aging Effects for Pressurizer

ML20132B593
Person / Time
Issue date:	12/13/1996
From:	Moulton J NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
PROJECT-683 TAC-M96277, TAC-M96278, TAC-M96279, NUDOCS 9612170311
Download: ML20132B593 (17)

Text

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k UNITED STATES s

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4 001

. g,o December 13, 1996 ORGANIZATION:

Babcock and Wilcox Owners Group (BWOG) l

SUMMARY

OF MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMIS-SION AND THE BWOG REPRESENTATIVES TO DISCUSS THEIR PROPOSED RESOLUTION OF STAFF OPEN ITEMS IN THE DRAFT SAFETY EVALUATION FOR BAW-2244, " DEMONSTRATION OF MANAGEMENT OF AGING EFFFCTS FOR THE PRESSURIZER". (TAC NOS. M 96277, M96278, & M 96279).

On November 6, 1996, the NRC staff met with representatives of the Babcock and Wilcox Owners Group (BWOG) to discuss their proposals to resolve the three open items in the staff's September 13, 1996 draft safety evaluation for the B&WOG, Generic License Renewal Program topical report, BAW-2244, "Demonstra-tion of the Management of Aging Effects for the Pressurizer." The list of meeting attendees is contained in Attachment (1) and the meeting handouts are contained in Attachment (2).

On the issue of potential pressurizer clad cracking, the BWOG asserted that it is not a potential aging effect for B&WOG and that the incident of clad cracking at one plant is not relevant because that incident was caused by a low pressurizer level event.

The NRC staff expressed their belief that +be one incident raises a concern that even normal level fluctuations in the pressurizer may lead to an increased potential for such cracking over time.

B&WOG stated that there is no experience with clad cracking due to normal pressurizer level transients and believed that the staff's concern is inappro-priate given the fact that the NRC has not taken any generic action for current operating plants.

The B&WOG agreed to attempt to provide additional justification why pressurizer clad cracking is not likely at B&WOG plants or propose a one-time inspection of the cladding.

On the issue of cracking of stainless steel safe-ends, the B&WOG agreed to consider the chemistry control program as an aging management program rather than as justification that the aging effect of cracking is not plausible.

However, the B&WOG objected to the staff's characterization of chemistry control as only capable of " inhibiting" cracking in one section of the draft safety evaluation.

The staff agreed to revise its safety evaluation to use the term " prohibits cracking" consistent with the other sections of the I

1 report.

On the issue of pressurizer heater partial penetration welds, the B&WOG stated tsgM that they perform a Category B-P examination because the welds are part of the UT bolted closure for the heater bundle. Additionally, they stated that the B-P Inspection is equivalent to B-E.

The staff questioned whether the B-P inspection for the heater bundle really is a focused look for leakage, since

@# J' the heater bundle may not be considered a bolted connection due to the l

existence of the seal weld modification. The B&WOG committed to confirming l

that the B-P inspection that is actually performed is in fact a focused leakage inspection around the heater bundle and is equivalent to B-E.

The i

staff still expressed their belief that a more intrusive inspection of the condition of the heater partial penetration welds, at least on a one time iA 3 170065 f Q 0 h h$ 3 NBC RLE CENTER CDPV 9612170311 961213 t

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. basis, is appropriate to determine their susceptibility to cracking.

The B&WOG agreed to consider committing to a one-time inspection of these welds in the course of the original operating term of a B&W plant when a replacement of a heater bundle is necessary.

Additionally, the B&WOG stated that they intended for the staff to make a finding on the adequacy of the scope of pressurizer components and did not believe that a renewal applicant action item to perform " scoping" on the pressurizer was appropriate.

The staff stated that they would consider this request.

Lastly, the B&WOG stated that they would provide their responses to the staff's open items in writing by November 22, 1996.

Project No. 683

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. No on, Project Manager cense Renewal Project Directorate ivision of Reactor Program Management Office of Nuclear Reactor Regulation Attachments:

1.

Meeting Handouts 2.

Meeting Attendees j

Service List (with all enclosures) plus R.L. Gill, Duke Power cc:

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Babcock and Wilcox Owners Group L

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iPfojecFNoI683:

Babcock & Wilcox Owners Group Gener-(

ic License Renewal Program cc:

Mr. Robert B. Borsum Regional Administrctor, Region IV Framatome Technologies U.S. Nuclear Regulatory Commission 1700 Rockville Pike 611 Ryan Plaza Drive, Suite 1000 Suite 525 Arlington, Texas 76011 Rockville, Maryland 20852 Mr. James J. Fisicaro hichael Laggart Director, Licensing Manager, Corporate Licensing Entergy Operations, Inc.

GPU Nuclear Corporation Route 3, Box 137G One Upper Pond Road Russelville, Arkansas 72801 Parsippany, New Jersey 07054 Earnest L. Blake, Jr., Esq.

Chairman Shaw, Pittman, Potts Board of County Commissioners and Trowbridge of Dauphin County 2300 N. Street, NW Daughin County Courthouse Washington, D.C.

20037 Harrisburg, Pennsylvania 17120 Regional Administrator, Region I Mr. J. W. Hampton U.S. Nuclear Regulatory Commission Nuclear Generation Vice President 475 Allendale Road Duke' Power Company King of Prussia, Pennsylvania 19406 Oconee Nuclear Station MC: ONO IVP B. Gutherman, Manager P.O. Box 1439 Licensing Seneca, South Carolina 29679 Florida Power Corporation (SA2A)

Crystal River Energy Complex Mr. John R. McGaha 15760 W. Powerline Street Vice President, Operations Support Crystal River, FL 34428-6708 Entergy Operations, Inc.

P.O. Box 31995 William Dornsife, Acting Director Jacksonville, Mississippi 39286 Bureau of Radiation Protection Pennsylvania Department of Regional Administrator, Region II Environmental Resources U.S. Nuclear Regulatory Commission P.O. Box 2063 101 Marietta St., N.W. Suite 2900 Harrisburg, Pennsylvania 17120 Atlanta, Georgia 30323 Chairman Mr. R. L. Gill Board of Supervisors GLRP Licensing Coordinator of Londonderry Township c/o Duke Power Company R.D. #1 Geyers Church Road EC-12R Middletown, Pennsylvania 17057 P.O. Box 1006 i

Charlotte, North Carolina 28201-Mr. J. E. Burchfield l

1006 Compliance Duke Power Company Oconee Nuclear Site P.O. Box 1439 Seneca, South Carolina 29679

December 13, 1996 2

basis, is appropriate to determine their susceptibility to cracking. The B&WOG agreed to consider committing to a on6-time inspection of these welds in the course of the original operating term cf a B&W plant when a replacement of a heater bundle is necessary.

Additionally, the B&WOG stated that they intended for the staff to make a finding on the adequacy of the scope of pressurizer components.and did not believe that a renewal applicant action item to perform " scoping" on the pressurizer was appropriate. The staff stated that they would consider this request.

Lastly, the B&WOG stated that they would provide their responses to the staff's open items;in writing by November 22, 1996.

1 Project No. 683 b

Original Signed By:

+

4 John P. Moulton, Project Manager l

License Renewal Project Directorate

' Division of Reactor Program Management Office of Nuclear Reactor Regulation Project No. 6834 MeetingAttende$s Attachments:

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Me'eting Handouts 2;

' Serv' ice List'(withlaillenclosures) plus:R.L. Gill, Duke Power

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RAM COPY:

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ACRS DISTMIENIS via e-sells FMiraglia/AThadent (A) (FJM)/(ACT)

RCorreia (RPC)

Ziaunerman (RPZ)

RWet.sman (RMW)

TMartin (TTM)-

JStrosnider (JRS2)

DMatthews (08M)

S0roggitis (SCD)

$Newberry (SFN)

$Peterson (SRP)

EJorden (JKR)

GLaines (GCL)

JMoulton (JPM1)

TSpels (TPS)

$ Flanders (SCF)

JMoore/EHolter (JEM)/(EJH)

RJohnson (REJ)

GMizuno (GSM)

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GHolahan (GMH)

PTKuo (PTK)

BSheron (BWS)

CRegan (CMRI)

G8agchi (GXB1)

HLBrasener (MLB)

DOCUMENT NAME:

110696.bwg Ta seesive a copy of this doeuenent, inaEcate in the bes:

"C* = Copy without attachment / enclosure "E" = Copy with attachment /encloswo

• N* = No copy 0FFICE-LA;PDLRs PM:PDLR g PD:PDIga/

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JMoultaf/r SNewtstry DATE If//1/9T '

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IP/.tf 96 0FFICIAL RECORD COPY

e LICENSE RENEWAL PROJECT DIRECTORATE MEETING WITH THE B&WOG PRESSURIZER DRAFT SAFETY EVALUATION OPEN ITEMS November 6, 1996 ATTENDANCE LIST NAME AFFILIATION John P. Moulton NRC/NRR/DRPM/PDLR Dave Firth B&WOG/FTI David Masiero GPU Nuclear Mark Rinckel B&WOG/FTI Frank Gregory B&WOG/FTI Mel Arey Duke Power Tricia Heroux for EPRI Stan P. Maingi PA - BRP Scott Flanders NRC/NRR/DRPM/PDLR Richard E. Johnson NRC/RES/EMMEB Robert Borsum FTI Robert Gill Duke Power Sam Lee NRC/NRR/DRPM/PDLR P.T. Kuo NRC/NRR/ DRPH /PDLR Christopher H. Regan NRC/NRR/DRPM/PDLR H.L. Brammer NRC/NRR/DE l

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B&WOG GLRP Pressurizer Report (BAW-2244) 1

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Responses to Draft Safety Evaluation Open issues l

November 6,1996 1

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Introduction Staff /GLRP l

e Open issues GLRP Pressurizer Clad Cracking Cracking of Stainless Steel Safe Ends Pressurizer Heater Partial Penetration Welds i

e Additional item GLRP n

Scoping l

e Written Response GLRP l

Schedule e

Closing Comments Staff /GLRP l

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1. 1 Pressurizer Clad Cracking l

l DSE GLRP e

Experience at one plant e

Cracking occurred due to indicates potential aging spray of cold water during a effect.

Iow-level event as documented by utility and l

industry reports.

e Inspection done at similar plant. As reported to NRC, no flaws detected.

e No generic communications issued regarding event.

e Clad cracking could e

Crack indications have been propagate into base reexamined and shown not metal.

to propagate during normal operation.

e Aging management e

Clad cracking not an aging i

program necessary.

effect for period of extended operation.

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1. 1 Pressurizer Clad Cracking I

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Recommended path to closure i

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Recommend SE be written to reflect follow up industry inspection activities.

e Closed.

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1. 2 Cracking of Stain ess Steel Safe Ends l

DSE GLRP Response i

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SCC of SS safe ends is e

SCC of SS safe ends is l

an applicable aging not an applicable aging i

effect.

effect due to water chemistry.

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SCC of SS safe ends not observed at any B&W operating plant.

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GLRP position consistent with RCS piping report.

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Water chemistry program o

Effective water chemistry inhibits cracking, does precludes SCC for SS l

not preclude cracking.

safe, ends.

e B&WOG propose o

GLRP will revise report to l

program to manage credit primary water general SCC of stainless chemistry program as an steel safe ends.

aging management i

program.

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1. 2 Cracking of Stainless Steel Safe Ends r7 j

Recommended Path to Closure i

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BAW-2244 to be revised to credit primary water l

chemistry program as an aging management l

program.

o Closed.

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1. 3 Pressurizer Heater Partial Penetration Welds w,n i

l DSE GLRP l

e Category B-E an e

Category B-P performed applicable inspection.

since part of bolted closure.

o Category B-P equivalent or superior to BE.

e 1993 Section XI Addenda l

recognizes duplicity and eliminates Category B-E.

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Staff does not believe e

B&W design different from that B&W heater welds other vendors; replacement substantially different bundles versus individual from other vendors.

heater nozzle welds.

e A more intrusive exam e

Insp ction requires heater necessary along with bundle removal. Leads to Category B-E.

increase in critical path time, radiation dose, and cost.

e Examination is a hardship, not justifiable.

e-Category B-P in concert with leakage detection adequate.

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1. 3 Pressurizer Heater Partial Penetration Welds 1

l Recommended path to closure e

if welds fail, leakage will be detected. Structural integrity of bolted closure will not be compromised.

e Category B-P in concert with leakage detection adequate.

e Closed.

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Action item #7 - Screening

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RESPONSE

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"Since the report was not e

BAW-2244 completely meant to be a complete covers the pressurizer listing..." (DSE Sect. 4.1) components.

e This Action Item should be dropped.

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Issue Summary i

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e issues Proposed to be Closed l

1. 1 - Pressurizer Clad Cladding

1. 2 - Cracking of Stainless Steel Safe Ends l

1. 3 - Heater Partial Penetration Welds 4

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e Action item #7 Proposed to be Dropped 4

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I Written Response Schedule ma;r w w.m 1

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e Letter documenting GLRP response will be

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submitted by November 15,1996.

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