ML20138J258

Summary of 970422 Meeting W/Wog to Give WOG Opportunity to Present Preliminary Response to Staff RAI Re Pressurizer Generic TR WCAP-14574, License Renewal Evaluation:Aging Mgt Evaluation of Pressurizers. List of Attendees Encl

ML20138J258
Person / Time
Issue date:	05/06/1997
From:	Prato R NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
PROJECT-683 NUDOCS 9705080117
Download: ML20138J258 (44)

Text

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UNITED STATES g

g NUCLEAR REGULATORY COMMISSION 4"

WASHINGTON, D.C. 20555-0001 o

May 6, 1997 4

ORGANIZATION:

Westinghouse Owners Group PROJECT:

Westinghouse Owners Group Generic Topical Reports

SUMMARY

OF THE MEETING BETWEEN THE U.S. NUCLEAR REGULATORY l

COMMISSION AND THE WESTINGHOUSE OWNERS GROUP TO DISCUSS THE REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE WESTINGHOUSE PRESSURIZER GENERIC TOPICAL REPORT 1

On April 22, 1997, member::-of the staff met with the Westinghouse Owners Group (WOG) to discuss generic topical report (GTR) WCAP-14574, " License Renewal Evaluation: Aging Management Evaluation for Pressurizers." The purpose of the meeting was to give the WOG an opportunity to present their preliminary response to the staff's request for additional information (RAI) relating to i

the initial review of WCAP-14574 and their current plans and schedule for submitting additional license renewal GTRs. A list of meeting attendees is provided as Attachment (1), and the meeting handout is provided as Attachment (2).

The WOG presented their preliminary response to the staff's RAls relating to WCAP-14574.

They presented their current thinking relating to each RAI, and the staft provided some additional clarification as to the intent of some of the RAIs.

The following are highlights of the key issues discussed:

In response to RAI No. la, WOG will provide a response consistent with l

the industry response that will be released soon.

i In response to RAI No. Ib, the WOG insurge-outsurge program is scheduled to be complete by the end of 1997 and is not related to Bulletin 88-11.

In response to RAI No.2, the staff provided additional clarification that an applicant needs to identify and justify any differences between the code edition that they are committed to at the time of application and the 1989 edition of ASME,Section XI.

In response to RAI No. 8, the WOG stated their position that external boric acid corrosion is event driven and, therefore, not an aging issue.

In response the RAI No. 9, the WOG presented its position that the i

pressurizer manway gasket is not long-lived because it has a qualified life of a single compression.

The WOG also discussed their current plans and schedule for submitting GTRs relating to license renewal.

The W0G informed the staff that they intend to submit a fifth license renewal GTR on reactor vessel internals by the eno of this month.

In addition to these five reports, the WOG informed the staff that they have completed five additional license renewal reports, and another five reports are near completion.

They expect to submit only another two or 9705080117 970506 f74/

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PDR TOPRP ENVW

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i three of these reports (e.g., cabling and HVAC) by the end of June 1997.

The remainder of the reports will not be submitted for ARC review, but will be used as guidance documents for perspective applicants to use in preparing a license renewal application.

d Robert J. Pra

, Mechanical Engineer License Renewal Project Directorate l

Division of Reactor Program Management Office of Nuclear Reactor Regulation Project No. 683 Attachments:

1. Attendance List

2. Meeting Handout i

cc w/atts:

See next page j

i

1 WESTINGHOUSE OWNERS GROUP (WOG)

Project No. 686 i

cc:

Mr. Gregory D. Robison l

Ad Hoc Technical Group Coordinator LCM /LR Working Group l

Westinghouse Owners Group Duke Power Company P.O. Box 1006 Charlotte, NC 28201 Mr. Sumner R. Bemis

)

l Westinghouse Owners Group Project Office l

Westinghouse Electric Corporation, ECE 5-16 1

P.O. Box 355 Pittsburgh, PA 15230-0355 Mr. Theodore A. Meyer Westinghouse Program Manager for WOG LCM /LR Program Westinghause Electric Corporation, ECE 4-22 P.O. Box 355 l

Pittsburgh, PA 15230-0355 i

l Mr. Gordon M. Vytlacil Westinghouse Lead Engineer for WOG LCM /LR Program Westinghouse Electric Corporation, ECE 4-22 P.O. Box 355 Pittsburgh, PA 15230-0355 l

Mr. Roger A. Newton l

Chairman, LCM /LR Working Group l

Westinghouse Owners Group Wisconsin Electric Power Company 231 West Michigan Milwaukee, WI 53201 l

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SCollins/FMiraglia (SJC1/FJM) l RZimmerman (RPZ)

MSlosson (MNS)

WDean (WMD)

PTKuo (PTK)

JFair (JRF)

LBanic (MJB)

HBrammer (HLB)

LLois (LXL1)

BElliot (BJE)

MHartzman (MXH)

DTerro (DXT)

KManoly (KAM)

RCorreria (RPC)

RWessman (RHW)

JStrosnider (JRS2)

GMizuno (GSM)

GHolahan (GMH)

BSheron (BWS)

GBagchi (GXBl)

RJohnson (RLJ2)

JVora (JPV) i

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Name Oraanization Robert Prato NRC-PDLR Mark Hartzman NRC-DE Barry Elliot NRC-DE Jim Brammer NRC-DE P.T. Kuo NRC-PDLR Roger Newton WEPCo/WOG Greg Robison Duke Power /WOG Jon Hornbuckle Southern Nuclear /WOG R.L. Sylvester Westinghouse /WOG B.B. Hood Westinghouse /WOG Mark Gray Westinghouse /WOG Scott Flanders NRC-PDLR David Roth Virgina Power /WOG Michael Henig Virgina Power /WOG Don Eggett Commonwealth Edison /WOG Charles Meyer Westinghouse /WOG Gordon Vytlacil Westinghouse /WOG 1

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l Meeting Purpose i

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e Describe WOG Degradation Management Categories e Discuss WOG Responses to l

Pressurizer RAls k

e Provide a Status of WOG Submittals i

e Discuss the WOG Need for Establishing an NRC Review Schedule l

Westinghouse Owners Group 2

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WOG Degradation Management Categories n,

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l e Different categories of degradation help j

organize management techniques e Categories'in order of the relationship to License Renewal:

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DESIG Ni (Initially no relationship) l EVENT v

1 AGING v

REGULATORY (Direct result of LR) i Westinghouse Owners Group 3

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DESIGN - Precludes aging effects l

from occurring

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e Based on:

Material selection Environmental stressors A

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e Examples:

Prevention - coatings or cathodic protection j

Mitigation - water chemistry l

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Westingn~ ouse Owners Group 4

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i EVENT - Degradation causing an a anormal environment

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e Aging degradation may result e Timely repair & restoration of the norma conditions can preclude aging degradation from occurring e Examples:

Leakage of bora:ed coolan:

Viaration caused by improper moun':ing 4

Westinghouse Owners Group 5

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AGING - Degrac ation under norma. conditions

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w-Degradation continues over time WOG generic aging management i

a programs - described using six attributes i

Types of aging management programs:

j 3 Condition monitoring - ISI or erosion-corroslon n Performance monitoring - heat transfer measurements

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Owners Group 6

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REGULATORY-Actionsidentified i

by the USXRC staff and commission

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l e Effects not recognized by the industry as related to aging 4

e Example - one-time LR inspection of pressurizer cladding i

e Actions performed when requested by i

the NRC i

I i

Westinghouse Owners Group 7

4

I Pressurizer Summary

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i e Section 2.0 - Scope, boundary, &

desc.riptions.

o Section 3.0 - Degradation evaluations e Section 4.0 - Aging management 1

programs j

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1 Westinghouse Owners Group 8

9 8

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Pressurizer Summary we==wamuwaauw~======~

1 e Identified potential e Non-significant aging aging effects:

effects:

Corrosion Creep Creep Erosion and Erosion and erosion / corrosion erosion / corrosion irradiation embrittlement Fatigue Stress relaxation Irradiation embrittlement Thermal aging Stress relaxation e Potentially significant Thermal aging aging effects:

Corrosion (SCC & PWSCC) n Fatigue Westinghouse Owners Group 9

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3 l

WOG Responses to XRC RAIs on the l

Pressurizer GTR, WCAP-14574, Rev. O j

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m e RAI No.1 1

i

a. In the discussion of the Industry Position on l

Fatigue Evaluation, provide a specific commitment l

to perform ari evaluation, using the most current i

environmental fatigue effects, for the period of extended operation.

1 i

b. Provide more detailed background information on the WOG program for pressurizer insurge-outsurge transients mitigation and discuss its relationship to NRC Bulletin 88-11.

Westinghouse Owners Group 10 i

WOG Responses to XRC RAIs on the Pressurizer GTR, WCAP-14574, Rev. O

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e Response to RAI No.1a The report will incorporate the revised proposed industry position on fa~tigue, which considers environmental effects for an: extended period of operation A generic screening evaluation, including environmental effects very conservatively, results in two additional components being potentially fatigue sensitive

- Safety and relief nozzles

- Instrument nozzles i

Westinghouse Owners Group 11

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i WOG Responses to XRC RAIs on the Pressurizer GTR, WCAP-14574, Rev. O

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,.,...,,a, e Response to RAI No.1b Background for.the ongoing WOG program is provided in Subsect: ion 2.6.1.

l The WOG insurge-outsurge program is l

schedu ed to be completed by end of 1997.

)

The program is not related to NRC Bulletin 88-11.

Westinghouse Owners Group 12

i l

l WOG Responses to XRC RAIs on the l

Pressurizer GTR, WCAP-14574, Rev. O

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e RAI No. 2 - In the " Position" s':ep 2 and j

other ap alicable sections, clarify references to j

ASME Section XI as the ' 989 Edition, and that any deviation should be reviewed and l

endorsed by the staff.

o Response to RAI No. 2 - In the " Position" step 2 and other a aplicable instances,Section XI requirements will be clarified to be j

those " endorsed by the staff" where ap aropriate.

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INestinghouse Owners Group 13 l

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WOG Responses to XRC RAIs on the Pressurizer GTR, WCAP-14574, Rev. 0

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e RAI No. 3 - For Step 2 of the " Position", describe how the proposed ISI program will provide a fatigue 3

aging management program that will prevent failure l

of the pressurizer under current design-basis loads j

. for the period of extended. operation.

I e Response to RAI No. 3 - Paragraph will be i

expanded:

j Industry-accepted criteria currently manage fatigue effects Adequacy of inspection periods dependent on meeting CLB cyclic commitments i

Westinghouse Owners Group 14 l

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l WOG Responses to XRC RAIs on the j

Pressurizer GTR, WCAP-14574, Rev. 0

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e RAI No. 4 - Revise Step 3 of the " Position" description to eliminate the reference to the PVRC l

report, since the staff has not endorsed Ref.17.

i e Response to RAI No. 4 - The PVRC reference

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will not be deleted:

n To arovide WOG utilities with a complete current status of activities related to environmental effects.

A clarification will be added to note that the staff i

4 j

has not endorsed the Ref.17 results at the time j

the report was written.

j Westinghouse Owners Group 15

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l WOG Responses to XRC RAIs on the Pressurizer GTR, WCAP-14574, Rev. 0

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e RAI No. 5 - WCAP-14574 states that the surc e nozzle is carbon steel, NUMARC 90-07 i

states that ii: is cast stainless steel - clarify

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e Response to RAI No. 5 - The surge nozzle is low alloy steel with stainless steel cladding l

and wrough : stainless steel safe ends l

SA 216 Gr. WCC Casting 4

SA 508 Cl 2a forging l

Westinghouse Owners Group 16 i

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i WOG Responses to XRC RAIs on the l

Pressurizer GTR, WCAP-14574, Rev. O m

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e RAI No. 6 - Evaluate IGSCC and describe the j

aging management program for welds and weld regions e Response to RAl No. 6 - No generic aging effects caused by IGSCC have aeen 1

i identified n Material selection c

Fabrication qualification / control Duration of off-normal chemistry is too short to cause degradation i

Westinghouse Owners Group 17

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WOG Responses to XRC RAIs on the Pressurizer GTR, WCAP-14574, Rev. O

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l e RAI No. 9 - Are manway gaskets in the scope of the LR Rule and are gaskets subject to an aging I

management review? Describe seal-welded Alloy 600 diaphragms and perform an aging management review

~

~

j e Response to RAI No. 9:

l Manway gaskets are within the scope of the Rule Manway gaskets are not subject to an aging management 4

review because they are replaceable based on a one-time use r

A description of Alloy 600 diaphragms is included in section 2.3.2 j.

Westinghouse owners Group 18 l

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l WOG Responses to XRC RAIs on the Pressurizer GTR, WCAP-14574, Rev. O e RAI No.11 - Identify components welded to the inside of the pressurizer and discuss management of cracking of these welds e Response to RAI No.11:

Internal components welded to the pressurizer (Sect. 2.3.4):

spray head coupling - SA 213 type 304 SS upper & lower heater support plate brackets - SA 240 type 304 SS surge nozzle retaining basket - SA 240 type 304 SS Material is not sensitized:

Material selectior Fabrication controls No generic aging effects.have been identified Westinghouse Owners Group 19 m

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e RAI No.12 - Discuss the age-related

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degradation experienced by thermal sleeves.

e Response to RAI No.12:

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No generic aging effects for Westinghouse l

pressurizer taermal sleeves have been identified 4

j Potential degradation

-flow induced vibration is not present in the 4

pressurizer I

-thermal effects considered in the design I

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Westinghouse Owners Group 21 4

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l WOG Responses to XRC RAIs on the l

Pressurizer GTR, WCAP-14574, Rev. 0 x.smgg;pp;gg gj.,

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e RAI No.13 - Provide additional details on the heaters and heater welds and j

discuss aging management of these l

components.

e Response to RAI No.13 - Additional details will be provided in section 2 1

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j Westinghouse Owners Group 22

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1 Heater Sheath 2

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Terminal Lugs 5

Hermetic Seal Receptacle 6

Rubber Booth / Lug Divider I

7 External Insulation Material (Ceramic Insulator) 1 8-1/4" Bolt i

9 1/4" lock Washer s

10 1/4" Nut 11 Hermetic Pressure Seal t

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1 WOG Responses to XRC RAIs on the l

Pressurizer GTR, WCAP-14574, Rev. 0

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i e RAI No.14 - Describe the provisions for examining heater penetration welds

e. Response to RAI No.14:

n Heater well to pressurizer weld ~is a ASME Code partial penetration weld to the lower head cladding Direct inspection of the internal weld is not practical Visual ins l5ection of external surfaces is performed j

in accordance with ASME Section XI IWB 3522 i

'Nestinghouse Owners Group 24 i

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4 WOG Responses to XRC RAIs on the l

Pressurizer GTR, WCAP-14574, Rev. 0

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e RAI No.19 - Are any small nozzles (e.g. -

l sampling and level) exemat from ASME Section XI examina:: ions?

e Response to RAI No.19:

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All small nozzles are attached by partial i

penetration welds to the cladding 4

i All are included in visual inspection of external l

surfaces in accordance with ASME Section XI IWB 3522 Westinghouse Owners Group 25 i

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e RAI No.15 - Discuss'the applicability of IEB l

79-17 to relief and surge nozzle stainless steel safe ends and any programs that may be applicable.

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e Response to RAI No.15 - IEB 79-17 is not applicable:

The normal environtment of the relief nozzle i

is steam 1

The surge line nozzle is not exposed to stagnant borated coolant Westinghouse Owners Group 26 9

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Pressurizer GTR, WCAP-14574, Rev. 0 h

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RAI No. 7 - The staff disagrees with the WOG conclusion that l

aging management for the cladding is not needed. Commit to a l

one-time LR inspection of the cladding and cladding welds e

Response to RAI No. 7 - The WOG maintains the position l

because~:

This is not a generic issue - cracking has only been l

n i

identified at Haddam Neck and has been attributed to a pre-l service operational transient l

The effect is not related to aging - subsequent inspections (20 years later) using more accurate techniques have l

determined that there has been no further crack propagation

)l Based on this information, the WOG does not want to recommend a generic one-time inspection l

Westinghouse owners Grog 28 i

i

WOG Responses to NRC RAIs on the Pressurizer GTR, WCAP-14574, Rev. O

-- 2 4

i e RAI No. 8 - The staff disagrees with the WOG conclusion that boric acid corrosion does not affect components and no aging management is needed.

e Response to RAI No. 8:

The WOG recognizes that boric acid can cause corrosion of external ferritic surfaces, however...

n Exposure of external surfaces to boric acid is an abnormal environment created by a leak (an event) n A program described in section 3, based on current activities, manages the event i

Westinghouse owners Group 29

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WOG Responses to XRC RAIs on the l;

Pressurizer GTR, WCAP-14574, Rev. 0

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e RAI No.10 - Desgribe the potential for corrosion of manway. cover and bolt holes

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e Response to RAl No.10:

~ Corrosion of bolt holes and the manway cover is caused by an event Prog rams to manage event driven effects will be described in section 3 Westinghouse Owners Group 30

i l

WOG Responses to XRC RAIs on the l

Pressurizer GTR, WCAP-14574, Rev. 0

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i e RAI No.13 - State the edition of the ASME Code referred to by the aging I

management attributes

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j e Response to RAI No.13 - References i

to the 1909 edition, or other editions I

approved by the staff, will be included in sec" ion 4.0 i

Westinghouse Owners Group 31 1

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WOG Responses to XRC RAIs on the l

Pressurizer GTR, WCAP-14574, Rev. O

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e RAI No.17 - Will the WOG rely on j

ASME Section XI Appendices Vil and Vill to ensure effective and reliable ultrasonic examinations?

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e Response to RAI No.17 - Use of j

Appendices Vil and Vill will be determined on a plant-specific basis as determined by the Code of record for j

the plant Westinghouse Owners Group 32

~

l WOG Responses to XRC RAIs on the Pressurizer GTR, WCAP-14574, Rev. O

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e RAI No.18 - Describe how generic communications and licensee l

commitments have been reviewed to

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determine potential aging effects e Response to RAI No.18 - The response l

will describe the process used by the i

WOG and Section 2.6 will be updated to identify any additional issues J

l Westinghouse Owners Group 33

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l WOG Responses to XRC RAIs on the Pressurizer GTR, WCAP-14574, Rev. O iw

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e RAI No. 20 - Discuss if pre-service or 4

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service induced flaws require an aging

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management program e Response to RAI No. 20:

There are no known service induced flaws Pre-service induced flaws are not caused by aging, therefore an aging management review is not required by the Rule i

Westinghouse Owners Group 34

4 Status of WOG Submittals n=

n- = _ n e-e RCS Su aports, WCAP-142 22, Rev. 2 -

l submitted 3/z /97, SER exaec':ed 7/97 e Pressurizer, WCAP-14572., Rev. 0 - RAls issued 1./14/97, Rev.1 expected 5/97 l

e RCS Piping, WCAP-14575, Rev. 0 -

submi':ted 8/28/96, RAls expected 4/97 o Containment, WCAP-1/ 756, Rev. 0 -

i submitted 12/11/96, RAls exaected 6/97 o RV Internals, WCAP-14573, Rev. 0 - to be publishec 4/97 i

Westinghouse Owners Group 35

WOG Xeec. for Esta alishing an XRC i

Review Schec ule

annan==

== mm-e Generic reports can recuce t7e LR effort for utilities and the NRC e NRC review fees 7 ave been partia ly waived 1

to recognize :he ceneric value of t7e GTRs e The WOG and NRC should work closely to ensure generic wor < is approved in time for utilities evaluating the feasibility of LR (1997-

'998) e Plan fu':ure alloca': ion & utilization "or GTR review of utility & NRC resources Westinghouse Owners Group 36 c.,

___..-_m,

i

. 1 i

three of these reports (e.g., cabling and HVAC) by the end of June 1997.

The remainder of the reports will not be submitted for NRC review, but will be i

used as guidance documents for perspective applicants to use in preparing a license renewal application.

4 i

I Robert J. Prato, Mechanical Engineer License Renewal Project Directorate l

Division of Reactor Program Management Office of Nuclear Reactor Regulation Project No. 683 Attachments:

1. Attendance List

2. Meeting Handout cc w/atts:

See next page i

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