ML20141H923

Summary of 970516 Telcon W/Niagara Mohawk Power Corp Re Licensee Plans for non-code Repair to Reactor Water Cleanup Sys Piping at Nine Mile Point Nuclear Station 1. List of Participants & Info Submitted by Licensee Encl

ML20141H923
Person / Time
Site:	Nine Mile Point
Issue date:	05/20/1997
From:	Hood D NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
TAC-M72442, NUDOCS 9705270175
Download: ML20141H923 (13)

Text

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[ \ UNITED STATES g j 2

NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 20066-4001 May 20, 1997 g . . . . . j#

LICENSEE: Niagara Mohawk Power Corporation .[# #

FACILITY: Nine Mile Point Nuclear Station, Unit No. I j

SUMMARY

OF TELEPHONE CONVERSATION OF MAY 16, 1997, ON NON-CODE

" REPAIRS OF NON-SAFETY RELATED REACTOR WATER CLEANUP SYSTEM WELD (TAC NO. M72442)

On May 16, 1997, the NRC staff participated in a telephone conference call 4

with Niagara Mohawk Power Corporation (NMPC) to discuss the licensee's plans ,

for a non-Code repair to the reactor water cleanup system (RWCU) piping at '

j Nine Mile Point Nuclear Station, No.1 (NMP-1). Participants are listed in Enclosure 1. Enclosure 2, which includes the information submitted by the licensee, was faxed to the NRC by the licensee prior to the telephone conference call.

BACKGROUND On the evening of May 15th, NMP-1 was shut down to repair a through-wall leak in the RWCU piping at the 33-FW-22 weld (isoable non-ASME Code, non-safety-related piping). Due to commitments made by NMP-1 in their Generic Letter (GL) 88-01 program, which includes this weld, they submitted all the relevant information that was available at the time to the NRC Project Manager. NMP-1 submitted that information so that they could receive approval on their proposed repair, which they needed before they would be allowed to restart.

NMPC also hired a consultant, MPR Associates, to assist with any analyses and evaluntions that might have been needed. These analyses and evaluations will be sLbmitted for NRC staff review. However, it should be noted that they are not required by NRC regulations.

DISCUSSION The repair proposed was a weld overlay on a weld that contains a through-wall flaw (pinhole leak) in the stainless steel portion of a bi-metallic weld.

This weld is in a portion of the RWCU piping that is non-safety related, 1 isolable, and is not ASME Code Class piping. The leak was suspected during previous operation, but could not be located. Upon the latest startup, during which main turbine imbalances were addressed, the leak was located and the .

plant shut down to address this problem. l The conference call was held at 1:30 p.m. EST to discuss the proposed repair of the pinhole leak in the weld and any additional information that would be required for staff rev'iew. The NRC staff established through this conversation that the basis for this request was that NMP-1 has a corwnitment for NRC approval in its GL 88-01 program. It was also established that this repair was in a non-Code, non-safety related, isolable part of RWCU piping.

The licensee stated that they had not performed a detailed root cause analysis g for this through wall flaw. However, primary evaluation indicated that this weld had been sensitized to intergranular stress-corrosion cracking due to jD1 1 970 PDR P

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? weld repairs made in 1997. It was further established that this repair would

be in accordance with the NRC approved GL-88-01 program, and all applicable  ;

i NRC regulatory guidance. t l'

After carefully considering the licensee action plan, and the fact that nondestructive examination cf three similar welds in the RWCU system yielded

! no indications, the NRC staff gave verbal approval (at approximately 2:30 p.m. t i EST) to the NMPC proposal and conveyed that this specific problem should not preclude NMP-1 from restart. This information was also relayed to the NRC Region I office and the NMP-1 resident inspectors.  !

FOLLOWUP '

r 1 The NRC staff requested that an updated request be submitted to the NRC staff

i. as soon as practicable. The request should identify all commitments made to '

i the GL 88-01 program, request a formal review, and provide the technical basis j for the action plan. NMP-1 committed to send it as early next week as i possible, acknowledging that Monday, May 19th was preferable. The licensee

! agreed to conduct the evaluation of the sizing of the weld overlay.

Sincerely, l

f {dA(ht~. [e_c _

Darl S. liood, Senior Project Manager i

Project Directorate I-I  :

Division of Reactor Projects - I/II l Office of Nuclear Reactor Regulation j Docket No. 50-220 2 .

Enclosures:

1. Participants 1 2. Background information l'

cc w/encls: See next page

Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit No. I cc:

! Mr. B. Ralph Sylvia Resident Inspector 2

Executive Vice President U.S. Nuclear Regulatory Commission Generation Business Group P.O. Box 126 ,

and Chief Nuclear Officer Lycoming, NY 13093 Niagara Mohawk Power Corporation Nuclear Learning Center Charles Donaldson, Esquire 450 Lake Road Assistant Attorney General Oswego, NY 13126 New York Department of Law 120 Broadway Mr. Richard B. Abbott New York, NY 10271 Vice President and General Manager -

Nuclear Mr. Paul D. Eddy Niagara Mohawk Power Corporation State of New York Nine Mile Point Nuclear Station Department of Public Service P.O. Box 63 Power Division, System Operations Lycoming, NY 13093 3 Empire State Plaza Albany, NY 12223 Mr. Martin J. McCormick, Jr.

Vice President Mr. F. William Valentino, President Nuclear Safety Assessment New York State Energy, Research, and Support and Development Authority Niagara Mohawk Power Corporation Corporate Plaza West Nine Mile Point Nuclear Station 286 Washington Avenue Extension P.O. Box 63 Albany, NY 12203-6399 Lycoming, NY 13093 Mark J. Wetterhahn, Esquire Mr. Kn. A. Dahlberg Winston & Strawn General Manager - Projects 1400 L Street, NW Niagara Mohawk Power Corporation Washington, DC 20005-3502 Nine Mile Point Nuclear Station P.O. Box 63 Supervisor Lycoming, NY 13093 Town of Scriba Route 8, Box 382 Mr. Norman L. Rademacher Oswego, NY 13126 .

Plant Manager, Unit I  ;

Nine Mile Point Nuclear Station Gary D. Wilson, Esquire P.O. Box 63 Niagara Mohawk Power Corporation Lycoming, NY 13093 300 Erie Boulevard West Syracuse, NY 13202 Ms. Denise J. Wolniak Manager Licensing Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O. Box 63 Lycoming, NY 13093 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

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TELECONFERENCE ATTENDEE LIST 5/16/97 Attendees HRC K. Wichman, NRR/DE/ENCB

- S. Bajwa, NRR/PDI-I W. Gleaves, NRR/PDI-1

Hjacara Mohawk Dave Baker, Licensing Dept. 1

. Marty McCormick, VP Engineering 1 Bill Yeager, Mgr. Engineering for Unit No.1 Mcia Lee, Mechanical Design for Unit No. I Pat Bartolini, Mechanical Design Lead for Unit No.1 {

l Jim Wadsworth, ISI Program Coordinator i

Roger Carreri, Mechanical Design  ;

Steve Leonard, Supr. Licensing Dept. '

Joe Thuoffe, Engineering Dept.

MPR Associates Jim Nastell Randy Trench j l

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l Enclosure 1 I

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f Y NIAGARA i uMOHAWK

! NINE MILE PO' INT NUCLEAR STATION

P.O. BOX 83, LYCOMING, NEW YORK 13093 i' '

, FAX COVER LETTER

! NINE MILE POINT UNIT 2 -

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j EBQM: FAX TELEPHONE NUMBER: (315) 349-1400 ff p hrGocl.

NAME: f DEPARTMENT: UCENSING/ ENVIRONMENTAL '

8 TELEPHONE NUMBER: 3 4 9 70 /e EAXl IQ: Sid h hatl>fet .3 d / 4 /5 2./ c h TOTAL NUMBER OF PAGES FAXED (INCLUDING COVER LETTER): _J_ _

DATE: TIME:

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'llAY-15-97THU19:07 VP OF HSAS U2 OPS BLD0 FAX NO. 315 349 2605 P. 02 i NIAGARA MOHAWK .  !

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l RE: Nine MilePoint Unit 1 i- DudmL No. 50-220 j DDR43 i  ;

hskfecer Generic Leater 30 01, "NRC k%n en KrSCC and RWR Amm=M* Sambalm

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! In accendanoo with Generic istter (GL) 88-01, *NRC Position on IGSCC in BWR Austenide j Stainless stool Piping" and the NRC's Safety Evaluation Raports (SER) for Nine Mile Paint 1 Unit 1 (NhlPI) on GL V8-01, dated May 15,1990 and June 24,' 1991, this letter is to Nguest i NRC appmval of a weld oveday repair. A through-wall pin hole leakin a bimetallic (carbon i 5 piping to slainless steel nozzle) weld (33-FW.22) in the non safety related and isolable portions of the Beactor Water Cleanup SyMam (RWCU) has been discavared. Based upon our evaluation and conArmed by our consultant MPR Inc., this leak resulted from a 7/16" axial crack that has been classified as having Intergranular Stress Corrosion r=#Ma* QOSCC) in an area that was syworked during replacement of the stainless steelpiping with carbrm steel piping in 1977 (see attached Radky.$Je Examination Report NDE Report 1-5.0(MP7 0005). Our plan to repair tds weld is to pr.6.m a weld overlay which willInters ibe structunal shcogth of the wakhnent such that it will withstand design basis loads.

The design of the oveday is being performed in ancordanos with NUREG 0313 Rev. 2 and alaments af ASME Code Case N504, which is endorsed in Regulatory Guide 1.147. 'Ibese

. analyses will be available for staff asview when completed on Pdday, May 16,1997. Once installed, the weld oveday will assure structuralintegrity of this wMmant.

To assure that this weld shilure is an isolated incident, NMPC will ji.dwm mMManal ultrasonic +=minations on a sample of thres **100 welds. This sample alze is based an the planned sample expansion criteria used dv4 outages for RWCU inspections perfanned to comply with GL 38-01. If additional k.dications arm (cumd, mil erf the welds in the RWCU system which are subjnct to OL 88 C1,. augmented laWon nquiremena will be la=aa*d.

_ _ . _ _ _ _ . . - ~ _ _ . _ _ _ . _ . . . _ _ _ _ _ . _ _ _ _ _ _ _ - __ _ _ . _ .

! IIAY-15-97 THU 19:08 VP OF NSAS U2 OPS Bl.D0 1 .

FAX NO. 315 349 2605 P.03 1

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5 Pass 2 i NMP1 bds performed ultrasonic (UT) muina*Irms on six welds in the RWCU system outside ef the t'aarminmant Isolation Valva (OV)in accordance with GL 88-01, Supplement 1. Of i

the six welds, three have been UT ===minad each neueling outage ihr the last three ey--%

cycles (RPO12,13, and 14). The sample expansion of three welds wi!! being the totalIGSCC.

j canagory 0 welds e--w outside of the CIVs to mine (two welds whleh have never basa

{ ====inad for GL 88 01 and one which was,.sbuity ereminad duririg RPO12). Therefore, ,

j 28 pescent of the welds (32) in this population win have been paminad; this includes 33-FW.~

j 22, which will be UT enminad and be rectanned to a IOSOC C@i B. It is to be noted

{ that weld 33-FW 22 was added to the GL 8801 program as part af the program review

! amooisend wishIma 96-0s.

! We curantly expoet the repair and augmented aramianHans to be completed by 2:00 p.m.,

i Friday, May 16,1997. A====Ing no further laWae are indicated based on results of the l three additional examinations, Nine Mils Point Unit 1 oculd be ready to resume operation

(mode switch to startup) as early as midnight on May 16,1997. Itis recognimod that restart i will require NRC approval for this weld repair and alated inspections. We stand ready to j support your review with any additional infonnation that may be requimd.

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• Sincealy,

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!. Ma&. ucCormair.

j Vice Praddant - Nuclear Fingineering

! nDM/GJG/cmk j Anuhmane l ac: Mr. H. J. Miller, Regional AdmiataW, Region I l Mr. R. R. Norris, Senior Realdent inspector l Mr. S. S. Bajwa, Acting Direcsor, Project Directorate 1-1, NRR l Mr. D. S. Hood, Senior Project Manager, NRR 1 Bacords Management y

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NOTES:

JALL N0ZZLES ARE 304 STAINLESS STEEL.

ALL PIPING IS CARBON STEEL, 6" ASTM A106 GR. B SCH. 80 EXCEPT FOR i FW-55 WHICH IS WELCCD TO 6" ASTM A376, TYPE 304 SCH. 80S STAINLESS STEEL IN0Z2LE. l THFSE WELDS ARE ALL PIPE TO N0ZZLE WELDS IN THE HIGH PRESSURE AND TEMPERATURE PIPING.

CPERAT ING PRESSURE IS APPROX. 1000 PS1G AND GPFRAT TNG TEMPERATURE IS IN THE RANGE FROM APPROX. 500 F TC 200 F. i NMPC REFERENCE DWG. C25852C SH.I

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33-FW-22 WELD OVER_AY REPA::R .

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\)3 PHOP3 SED WFs E TWFf4 Ay 368 XOREES AROUM) EXIlleNG A02?LE/FIP-

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AIDS, CP, B ."

' W' p' g ' TOE *0F WELD BETWEEN N0ZZLI Aft 0 EXIS11NG DISSiHILMt '

F t 1/4 PIPE.STANLESS STEEL S!K & WELL HETAL WELO ~ ^ ~ ~ ~

33-W-22 BiSTAG DETERMINEE Bf AMOUNI 0F s \ Y

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DISTRIBUTION l

HARD COPY (with enclosures 1 & 2))

Docket File PUBLIC' PDI-l Reading OGC ACRS l

E-MAIL (with enclosure 1 only) '

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-Sr-Gel 1%s/F.Miraglia- I R. Zi m.r.  !

l S. Varga

-J. ZwlinskiM S. Bajwa l

D. Hood S. Little i D. Ross (e-mail to SAM) l, W. Gleaves i M. Callahan i' Gr4a4M Jr-Strosnider A l K. Wichman l K.' Cotton W. Dean L. Doerflein, RI t

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weld repairs made in 1997. It was further established that this repair would be in accordance with the NRC approved GL-88-01 program, and all applicable NRC regulatory guidance.

After carefully considering the licensee action plan, and the fact that nondestructive examination of three similar welds in the RWCU system yielded no indications, the NRC staff gave verbal approval (at approximately 2:30 p.m.

EST) to the NMPC proposal and conveyed that this specific problem should not preclude NMP-1 from restart. This information was also relayed to the NRC Region I office and the NMP-1 resident inspectors.

~

4 FOLLOWUP The NRC staff requested that an updated request be submitted to the NRC staff as soon as practicable. The request should identify all commitments made to the GL 88-01 program, request a formal review, and provide the technical basis for the action plan. NMP-1 committed to send it as early next week as possible, acknowledging that Monday, May 19th was preferable. The licensee agreed to conduct the evaluation of the sizing of the weld overlay.

Sincerely, h $W kC

/

Darl S. H,.od, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosures:

1. Participants

2. Background information cc w/encls: See next page DOCUMENT NAME:NMP72442.TEL To r:ceive a copy of this document, indicate in the box: "C" - Copy without attachment / enclosure "E" - Copy with attachment /englosure "N" - No copy 0FFICE PM:PDI-1 lE PM:PDI 1 lE LA:PDI-1 M l D:PDI-1 ,,p % l I l

,NAME WGleaves:mw W (o DMood w(4 t -, e SLittle F SBajwa //

• P DATE 05/./o /97 05/ n /97 05/ @ /97 05/qB97 05/ /97 Official Record Copy

,