ML20062B617

Summary of 820714 Meeting W/Util & Westinghouse in Bethesda, MD Re Exams & Evaluations Concerning Thermal Sleeves

ML20062B617
Person / Time
Site:	Mcguire, McGuire
Issue date:	07/28/1982
From:	Birkel R Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8208040638
Download: ML20062B617 (33)

Text

l JUL 2 81982 Docket Nos: 50-369 and 50-370 APPLICANT: Duke Power Conpany FACILITY: McGuire Nuclear Station, Units 1 and 2

SUMMARY

OF MEETING Hf.LD CH JULY 14, 1982 ,

1 A necting was held with the Duke Power Company on July 14, 1982, in Bethesda, tiaryland. The purpose of the meeting was to discuss examinations and evaluations l perfomed by Duke Power Company regarding detached themal sleeves. A list of attendees is presented in Enclosure No.1. The agenda for the meeting is shown on Enclosure No. 2. Enclosure No. 3 presents viewgraphs used during the licensee ,

presenta tion. l The t'cGuire Huclear Station, Unit 1, was shutdown on June 23, 1982, for purposes of eddj current testing of all Model D steam generators. Pursuant to recent evidence of the degradation of themal sleeve components in the reactor coolant systen of the Trojan plant, another Westinghouse plant, the licensee promptly initiated an inspection of all themal sleeves in the Unit i reactor coolant systen utilizing radiography techniques. The RCS contains the following themal sleeves: (4) -10" accumulator nozzle cold leg, (2) -3" charging nozzle cold legs and (1) -14" pressurizer surge nozzle hot leg.

The radiograph of the 10" accumulator nozzle themal sleeve on loop B revealed j that it was detached and missing. This was confimed by the licensee by a visual inspection with a small TV camera going through the upstrean check valve on the 10" line. The licensee has inspected all other connections to the RCS having similar themal sleeves to assure that the remaining sleeves were in place with their welds intact. Only one detached (B loop) themal sleeve was evidenced by the licensee's inspection. The licensee reported that the loop B 10" line welds-located at the top of the sleeve had failed at the interface to the nozzle wall with possibly only a small portion of one weld remaining on the nozzle vall. The nozzle wall, according to the licensee, showed no indication that the sleeve had broken apart prior to being released. As a result of nonitoring of the lower reactor vessel area for loose parts during low flow and normal RCS flow conditions, the licensee concludes that the missing 10" themal sleeve is located in the lower reactor internals and that the small impacts during low flow conditions are of a minor nature. No movenent is indicated when full flow is present. The licensee considers this to indicate that the sleeve is parked and remains fixed in place.

The licensee presented the results of detailed stress analysis for the accumulator and other nozzles without themal sleeves as well as a description of the inpact and wedging effect of a loose themal sleeve on reactor internals. The potential hydraulic effects of tne detached thermal sleeve was also discussed. The licensee by letter dated July 13, 1982, documented all of the infomation provided during the meeting.

8208040638 820728 PDR ADOCK 05000369 PDE p ...................... .......................

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As a result of discussions with the licensee and Westinghouse and review of the infomation provided in its July 13, 1982, letter, the staff, at the conclusion of the meeting, indicated that continued operation of ticGuire Unit i until the next refueling outage or outage of sufficient duration, with the thermal sleeves as presently positioned is acceptable without undue risk to the health and safety of the public.

Ralph A. Sirkel, Project Manager Licensing Branch flo. 4 Division of Licensing

Enclosures:

As stated cc: See next page orrect > .E 1 B..f4.N ....DbNJ4.. . E.f.l..$..'.'6,k... . . . . . . . . . . .. . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .

SURNAME) ,e),(,hmc ,,E A,de 4, sam,, , M,Q,~,0 fy,,5,,!y, , , , , , , , , , , , , , , , ,, , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , ,

omy . 71.fl.82.. . . 7./,Ml.S2,,, , ,,,q,fJ,7 f,7,d , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , ,

NRC FORM 318 (10-80) NROM 024a OFF1CIAL RECORD COPY use mi-m wo

> c n ATTENDANCE LIST McGUIRE NUCLEAR STATION, UNITS 1 AND 2 July 14,19ti2 Duke Power Company W. H. Sample G. S. Lanady W. O. Parker, Jr.

Hal B. Tucker N. A. Rutherford R. E. Harris Westinghouse M. J. Zegar W. C. Gangloff J. c. Hoel sel D. G. Maire D. W. Alexandra R. W. Beer Don White W. R. Spezialetti F. J. Twogood K. C. Chang NRC Staff R. A. Birkel R. A. Purple W. S. Hazelton Joe Holonich R. L. Tedesco S. Hou R. Bosnak C. D. Sellers H. F. Conrad L. Frank Q L. Engle E. Murphy C. Y. Cheng C. Trammell E. Adensa:n F. Orr Wm. J. Collins (IE-HQ)

P. R. Bemis (RII)

A. R. Herdt (RII)

J. A. Olshinski (RII)

Other Jack McEuen (Tech. Services International)

U. '.i. i.i gpard (VUcu? '

orr.ce > . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..E ....R. . 21. tit.. 41r ...QEl>C.o.).. . .. ..

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oaTe y . . . . . . . . . . . . . . . . . . . . . ...................... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

sac ronu sia no-sopacu o24o OFFICIAL RECORD COPY usem >=i-ax u i 1

l McGuire Mr. William O. Parker, Jr. ,

Vice President - Steam Production Duke Power Company )

P.O. Box 33189 422 South Church Street Charlotte, North Carolina 28242 l cc: Mr. A. Carr James P. O'Reilly, Regional Administrator !

Duke Power Company U.S. Nuclear Regulatory Commission, P.O. Box 33189 Region II 422 South Church Street 101 Marietta Street, Suite 3100 Charlotte, North Carolina 28242 Atlanta, Georgia 30303 Mr. F. J. Twogood Power Systems Division Westinghouse Electric Corp.

P.O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. G. A. Copp Duke Power Company Steam Production Division P.O. Box 33189 Charlotte, North Carolina 28242 Mr. J. E. Houghtaling NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Mr. Jesse L. Riley, President The Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 J. Michael McGarry, III, Esq.

Debevoise & Libermian 1200 Seventeenth Street, N.W.

Washington, D. C. 20036 She'lley Blum, Esq. -

1716 Scales Street Raleigh, North Carolina 27608 .

Mr. Paul Bemis Senior Resident Inspector c/o U.S. Nuclear Regulatory Commission P.O. Box 216 Cornelius, North Carolina 28013

Enclosure 1 o, s ATTENDANCE LIST McGUIRE NUCLEAR STATION, UNITS 1 AND 2 July 14, 1982 Duke Power Company W. M. Sample G. S. Lanady W. O. Parker, Jr.

Hal B. Tucker N. A. Rutherford R. E. Harris Westinghouse M. J. Zegar W. C. Gangloff J. c. Hoel sel D. G. Maire D. W. Alexandra R. W. Beer Don White W. R. Spezialetti F. J. Twogood K. C. Chang NRC Staff R. A. Birkel R. A. Purple W. S. Hazelton Joe Holonich R. L. Tedesco S. Hou R. Bosnak C. D. Sellers H. F. Conrad L. Frank L. Engle E. Murphy

, C. Y. Cheng

'2 C. Trammell i

E. Adensam F. Orr Wm. J. Collins (IE-HQ)

P. R. Bemis (RII)

A. R. Herdt (RII)

J. A. Olshinski (RII)

Other Jack McEwen (Tech. Services International)

D. W. Lippard (VEPCo)

E. R. Smith, Jr. (VEPCo)

. 5nclosure2 AGENDA FOR MEETING WITH NRC McGuire 1 Reactor Coolant System Thermal Sleeves July 14, 1982 I. Introduction - W. O. Parker, Duke Power Co. ,

II. Statement of Problem A. Dascription of Thermal Sleeves -

Marty Zegar, h[

B. Thermal Sleeves - Inspection and Loose Part Monitoring Results - Morris Sample, Duke Power III. Safety Evaluation A. Nozzle Integrity without Thermal Sleeve -

Dr. Ken Chang, h[

B. Loose Thernal Sleeves -

Dave Maire, h[

1. Impact with RCS Componegts

2. Flow Maldistribution IV. Proposed Action by Licensee -

Morris Sample, Duke Power A. Augmented Monitoring for Loose Parts B. Additional Operator Training C. Augmented Inspections D. Schedule for Plant Operation - Hal Tucker, Duke Power

1. Removal of Loose Thermal Sleeve

2. Removal of Installed Thermal Sleeves V. Conclusions

. , . , , - , - . , . , ..-,,,.m... ,- ,.

T~'~. ,

Enclosure 3

DUKE THERMAL SLEEVE INVENTORY .

e REACTOR COOLANT PIPING UD 10" ACCUMULATOR N0ZZLES COLD LEGS .

(2) 3" CHARGING N0ZZLES COLD LEGS

(.D 14" PRESSURIZE SURGE N0ZZLE HOT LEG s

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INSPECTION PROGRAM

SUMMARY

July 1 -

Radiographic examination of 10" lines began.

July 1-4 -

RT results ' indicated thermal sleeves in place on Loops A~, C, and D.

July 5 -

RT results on Loop B 10" line indicated thermal sleeve missing.

Confirmed by visual inspection early on July 6. l l

July 6 -

Radiographic examination on 3" lines on Loop A and D showed sleeves in place and welds intact.

July 7 - Additional visual inspection of Loop B 10" line showed no sleeve '

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l July 7 - Radiographic examination of 14" line on Loop B showed sleeve  ;

in place and welds intact.

July 8 - Additional RT on remaining sleeves in 10" lines showed welds intact.

July 10 -

During operation of decay heat removal system minor impacts in lower reactor vessel internals.

July 11 -

During reactor coolant pump runs minor impacts with one pump running, no movement with all 4 pumps running.

n - -

EVALUATION OF RCL N0ZZLE WITHOUT THERMAL SLEEVE _

l N0ZZLES

- GEOMETRY AND MATERIAL

- MODELING

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. 2-D FINITE ELEMENT

- TRANSIENT DEFINITION

- HEAT TRANSFER ANALYSIS

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CONCLUSIONS 3" CHARGING N0ZZLE D MODEL .

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a SAFETY EVALUATION OF LOOSE THERMAL SLEEVES I. N0ZZLE INTEGRITY WITHOUT SLEEVE II. MECHANICAL EFFECTS OF LOOSE OBJECT A) REACTOR COOLANT PIPE B) STEAM GENERATOR C) REACTOR COOLANT PUMP D) REACTOR INTERNALS E) REACTOR VESSEL F) OfHERRUSCOMPONENTS G) AUXILIARY SYSTEMS l H) MATERIALS l

t III. Flow BLOCKAGE EFFECTS

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i O MECHANICAL EFFECTS ON STEAM GENERATOR 9 IMPACT FORCES WILL NOT VIOLATE REACTOR COOLANT PRESSURE BOUNDARY I

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o PUMP ISOLATED FROM HOT LEG SLEEVE BY STEAM GENERATOR TUBES I

e COLD LEG SLEEVES ARE DOWNSTREAM OF PUMP e REVERSE FLOW DURING STARTUP COULD MOVE OBJECTS TO PUM,P. IMPACT FORCES UPON RESTART OF PUMP WOULD,,NOT VIOLATE REACTOR COOLANT PRESSURE BOUNDARY. 4 ,.

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l 8 MECHANICAL EFFECTS ON REACTOR INTERNALS (CONTINUED) e LOWER INTERNALS IMPACT LOADS ON CORE BARREL ARE ACCEPTABLE LOADS DUE TO OBJECT WEDGED IN RADIAL KEY GAPS ARE ACCEPTABLE LOADS DUE TO OBJECT WEDGED UNDER SECONDARY CORE SUPPORT ARE ACCEPTABLE IMPACT LOADS FROM LOOSE OBJECT IN LOWER INTERNALS PACKAGE ARE ACCEPTABLE

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9 MECHANICAL EFFECTS ON REACTOR INTERNALS S UPPER INTERNALS l REVERSE FLOW DURING STARTUP COULD MOVE OBJECTS TO UPPER INTERNALS. IMPACT FORCES ACCEPTABLE.

LARGE SIZE OF PIECES AND FULL FLOW PRIOR TO CRITICALITY WOULD PREVENT OBJECTS FROM

! ENTERING GUIDE TUBES ROD STEP TESTS CONFIRM OPERABILITY OF CRDM DRIVE LINES ' EXISTING ANALYSES CONSIDER ONE STUCK CRDM

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MAKE-UP CAPABILITY.,

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4 i

S MECHANICAL EFFECTS ON AUXILIARY SYSTEMS l

e J.(Di PROBABILITY OF OBJECTS ENTERING AUXILI ARY SYSTEMS (CVCS AND RHR) l

-e FAILURE OF SINGLE PUMP, VALVE, ORIFICE, ETC.

WOULD NOT CREATE A SAFETY CONCERN ~

a SAFETY EVALUATION ~ CONCLUSION ADEQUATE ASSURANCE EXISTS THAT SAFE PLANT OPERATION IS NOT COMPROMISED BY FAILED THERMAL SLEEVES

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9 MATERIALS e NO UNACCEPTABLE MATERI ALS INVOLVED I

e MINOR STAINLESS STEEL CLADDING DAMAGE ON RV AND SG PRESENTS NO SAFETY CONCERN

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l 0 FLOW BLOCKAGE EFFECTS e CONSIDERED BLOCKAGE AT FUEL, LOWER INTERNALS, STEAM GENERATOR TUBES, LOOP PIPING AND AUXILIARY SYSTEMS l

e CONSIDERED NORMAL OPERATION AND TRANSIENT CONDITIONS e SIZE AND CURVED GEOMETRY OF PIECES RESULT IN NO SIGNIFICANT FLOW BLOCKAGES l

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A Ge.pso N N o C. AN I o td.5 l

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]. 'c ADDITIONAL" ACTIONS j

VERIFICATION OF LPM CALIBRATION AUGMENTED LPM DURING RESIDUAL HEAT REMOVAL OPERATION AND REACTOR COOLANT PUMP RUNS 1

INCREASE SURVELLIENCE FREQUENCIES FOR CONTROL ROD OPERABILITY INCORE FLUX MAP AND REACTOR COOLANT ACTIVITY SPECIAL PROCEDURE FOR LOOSE PART ALARM RESPONSE 4

/

M- -

MEETING

SUMMARY

DISTRIBUTION

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' Docket No(s)f750-369/370 NRC/PDR JUL 2 81982 Local PDR TIC /NSIC/ TERA #

LB #4 r/f Attorney, OELD OIE -

E. Adensam Project Manager R. Birkel Licensing Assistant M. Duncan NRC

Participants:

R. A. Birkel R. A. Purple W. S. Hazelton .

Joe Holonich R. L. Tedesco ,

S. Hon R. Bosnak C. D. Sellers H. F. Conrad L. Frank L. Engle -

E. Murphy C. Y. Cheng C. Trammell E. Adensam F. Orr i Wm. J. Collins (IE-HQ)

I P. R. Bemis (RII)

A. R. Herdt (RII)

J. A. Olshinski (RII)

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! bec: Applicant & Service List l

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