ML20204B311

Summary of 881006 Meeting W/Util in Rockville,Md Re Util Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs

ML20204B311
Person / Time
Site:	Summer
Issue date:	10/14/1988
From:	Hayes J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
IEB-88-008, IEB-88-8, NUDOCS 8810200200
Download: ML20204B311 (55)

Text

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October 14, 1988 Docket No. 50-395 DISTRIBUTION See raxt page LICENSEE: South Carolina Electric & Gas Company FACILITY: V. C. Sumer Nuclear Station

SUMMARY

OF OCTOBER 6, 1988 MEETING WITH SOUTH CAR 0 Lit;A ELECTRIC & GAS COMPANY General On October 6,1988, the NRC staff met with tne South Carolina Electric & Gas Company (SCE&G) and their consultant, the Westinghouse Corporation, to discuss SCELG's response to NRC Bulletin, 88-08, "Thermal Stresses in Piping Connected To Reactor Coolant Systems" for the V. C. Sunner Nuclear Station. The meeting i was held at fleedquarters in Ruckville, Maryland. A list of those persons who attended the meeting is included :s Enclosure 1. The agenda for the meeting is included as Enclusure 2.

Discussion At the meeting the SCE&G program for monitoring locations potentially sensitive to thermal stresses was presented by Westinghouse. Part of the presentation consisted of the priccity schete for the selection of the locations to be monitored and inspected and the physical depiction of the location of the piping potentially susceptible to thermal stresses. Enclosure 3 is the handout which was presented by Westinghouse. Some of the information presented in this handout was considered of a proprietary nature by Westinghouse. The NRC will make a determination as to whether this information should be considered proprietary. Until this determinaion is made, the page designated as proprietaty will be kept from toe public record.

At the conclusion of the meeting it was determined by the NRC staff that the program proposed by SCE8G was considered acceptable for the present refueling outage. However, the staff requested that SCE&G submit, prior to restart, their future plans and schedule for inspecting and monitoring the locations potentially susceptible to thermal stresses which are not a part of the present inspection and monitoring program. In addition, SCE&G was advised that their submittal should also indicate what actions they wili take in terms of analysis and evaluation in the event that the presence of therr.al stratification in one of the pipes is detected at a monitoring location.

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dohn J. Ilayes, Jr., Project Manager Project Directorate !!-1 Division of Reactor Projects I/II

Enclosures:

As stated cc: w/ enclosure See next page Dr

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8810200200 881014 PCR ADOCK 05000395 O PDC

DISTRIBUTION FOR fiEETING SUf'JiARY DATED: October 14, 1988 Facility: V. C. Sumer Nuclear Station, Unit No.1

Docket' File-NRC PDR Local PDR PDil-1 Reading E. Adensam J. Hayes OGC E. Jordan (MNBB3302)

B. Grimes (9A2)

J. Durr RI P.Kuof9H3)

!!. Hum (9H15)

R.Hermann(7E23)

M. Hart: man (9H3)

J. Lee (801)

H. Dance RI!

E. Reeves ACRS (10)

B. Troskoski (17D19) cc: Licensee / Applicant Service List

1 Mr. O. S. Bradham South Carolina Electric & Gas Company Virgil C. Susmer Nuclear Station cc:

Mr. William A. Williams, Jr.

Technical Assistant - Nuclear Operations Santee Cooper P.O. Box 764 (Mail Code 153)

Columbia, South Carolina 29218 J. B. Knotts, Jr., Esq.

Bishop, Cook, Purcell and Reynolds 1400 L Street, N.W.

Washington, D. C. 20005-3502 Resident Inspector /Susmer NPS c/o U.S. Nuclear Regulatory Cornission Reute 1, Box 64 Jenkinsv111e, South Carolina 29065 Regional Administrator, Region II U.S. Nuclear Regulatory Cosmission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairr,an, Fairfield County Council P.O. Box 293 Winnsboro, South Carolina 29180 Attorney General Box 11549 Columbia, South Carolina 29211 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 South Carolina Electric & Gas Company Mr. A. R. Koon Jr Nuclear Licensing ., Man.:ger Virgil C. Susmer Nuclear Station P. O. Box 88 Jenkinsville, South Carolina 29065

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ENCLOSURE 1 ATTENDANCE  ;

SEPTEM8ER 21. 1988 i NRC SCE&G WESTINGHOUSE OBSERVER J. Hayes, Jr. A. Monroe A. Chan A.Wyche(Bechtel) i J. Ourr D. Moore W. Bamford i P. Kuo A. Barth S. Palusamy I M. Hum S. Swantner N. Hartzman J. Wizz R. Hermann S. Lee i E. Reeves i

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ENCLOSURE 2 uma MiurTIM WI1H SOUIH Cha0 LINA METRIC & GAS OCKEER 6,1988 PURPOSE: 10 DISCUSS SCEhG'S RESPONSE TO NRC BULLETIN 88-06, "1NEIMAL 811MfWm IN PIPIM 00tMECTED 10 REACKR 000Udfr SYSTB6" FOR 1HE V. C. SIMIER NUCLEAR STATIN.

ITDtB 10 BE DISCUSSED: 1) SIMER PROGRAM

2) PRIORITY SCHDS FOR SEIAUTDG 14 CATI 0tE TO M INSPECTED.

3) IDCATIM OF PIPING POTBfrIALLY SUSCIPTINA 10 1HERMAL ST N .

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ENCLOSURE 3 .

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SOUTH CAROLINA  ;

. ELECTRIC & GAS COMPANY I

Actions to Address NRC Bulletin 88-08 1

and Supplements 1 and 2, Thereto i P

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i V.C. SUMMER PROGRAM TO COMPLY WITH NRC BULLETIN 88-01  ;

i I. onenina Statement Goal of Meeting I

II. Backaround of Issue

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Farley Unit 2  :

Ti'hange Unit 1 [

l III. Pinina System Review I

- Objective -

Selection Criteria f Rasults ,

i IV. Inspection Location Selection  :

t Objective  !

Selection Criteria (

Results  !

t V. Prioritization of Inseection Locations i

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- Objective l Selection Criteria  !

Results (

l VI. Monitorina Plan i

Objective I Selection criteria l Results l I

VII. NDE Techniaues l f

- Application to NRCB 88-08 {

t VIII. Summary

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SOUTH CAROLINA  !

ELECTRIC & GAS COMPANY .

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i WESTINGHOUSE CORPORATION  !

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I Responsible Programs to Address Concerns of NRC Bulletin 88-08  !

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j Identification of Applicable Lines and Our l

l Plan of Action forInspection and Monitoring l l l

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APPLICABLE LINES

1. Safety injection to Hot Leg Loop "A"

2. Safety injection to Hot Leg Loop "B"

3. Safety injection to Hot Leg Loop "C"

4. Safety injection to Cold Leg Loop "A" 1 S. Safety injection to Cold Leg Loop "B"

6. Safety injection to Cold Leg Loop "C"

7. Normal Charging 1

8. Alternate Charging

9. Auxiliary Pressuri7.er Spray i

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IDENTIFICATION OF INSPECTION LOCATIONS

• 2 Most Critical Lines l

1) Safety injection, Cold Leg, Loop A

2) Safety injection, Hot Leg, Loop C l Total of 9 UT inspection Locations '

(7 Welds,2 Elbows) e 7 Less Susceptible Lines

1) Safety injection, Cold Leg, Loop B

2) Safety injection, Cold Leg, Loop C

3) Safety injection, Hot Leg, Loop A

, 4) Safety injection, Hot Leg, Loop B

! 5) NormalCharging

6) Alternate Charging  !

The most critical weld on each line for a total of 6 UT locations i *

7) Auxiliary / Pressurizer Spray 1 UT inspection on main pressurizer spray line; 3 PT inspections on 2 welds plus soccolet weld; total of 4 inspection locations.

CONTINGENCY PLAN F

1. Any indication identified will be evaluated to determine the cause (if possible) and the appropriate actions will be taken to assure plant safety is maintained (i.e., repair, replace, fatigue evaluation, etc.).

2. For any inspection location identified as having indications that are potentially the result of stratification or thermal cycling, all locations (welds and elbows) on that line will be inspected.

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9 MONITORING Utilizing Resistance Temperature Detectors (RTD's)

Mounted on Piping '

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1 Xm e Pipe O.D.

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MONITORING CAPABILITIES l

INSIDE OUTSIDE CONTAINMENT CONTAINMENT M

RTD - - PERSONAL USEABLE DATA DATA LOGGER - _

COMPUTER TABLES , CH ARTS M

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CONCLUSIONS 1

1 e Responsible Programs Being implemented to

Address NRC Concerns 1

-- NRC Information Notice 88-01

! -- NRC Bulletin 88-08 l

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O WESTINGHOUSE SCE&G has solicited the support of Westinghouse to combine their knowledge of Industry Experience with Virgil C. Summer Nuclear Station plant specific conditions to help arrive at a program to address the bulletin requirements in a safe and responsible manner.

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BACKGRalND OF THE ISSUE: FAILURE EXPERIENCE 9 FAR.EY UNIT 2 (DEC. 87) e TIHANGE UNIT 1 (JUNE 88)

s" FAPLEY UNIT 2 RHR /SI LINE CRACKING e 12/8/87: LEAK IDENTIFIED AFTER CONIAINf/ENT COOLER DRAIN POTS NOTED AS ABNORb' ALLY HIGH: AND UNIT SHUT DG4N 8 LEAK RATE AT HOT STN4DBY: LESS THAN 1 GPM 8 SINGLE CRACK, CIRCUbfERENTI AL, 6" LONG (10), 0,5 ' LONG (00) 8 FAILURE INVESTIGATION CONFIRfED STRATIFIED FLOV HAD C/LISED FATIGUE CYCLES, AS CONFIRhED BY STRI ATIONS S N0 f/ATERI AL, CHEMISTRY, OP OTHER LOADING ASNORfVLITIES WERE FOUND 8 SOURCE OF THERf/AL CYQ.ING: LEAKAGE FLOV FROM A HIGH PRESSURE, COOLER WATER SOURCE UPSTREAM OF THE CHECK VALVE (THIS WAS VERIFIED BY THERb'AL MONITORING ON THE PlPE) e CYCLING ELIMINATED BY DIRECTING LEAKAGE TO ANb'HER PATH 8 FUPTHER INSPECTION SHG4ED NO CRACKING IN OTHER LINES

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TlHANGE UNIT 1 RHR/S1 LINE CRACKS 0 6/18/88: LEAK DETECTED FROM REACTIVITY AND MOISTURE INCREASES S LEAK RATE WAS 6 GPM e 4 CRACKS, THE LARGEST OF WHICH WAS 3.5" LONG (10), 1.6" LONG i

(00), IN THE ELBOW. OTHER CPACKS IN PIPE AND AT WELD 1

3 0 ETALLURGICAL INVESTIGATION CONFIRED THERR FATlGUE AS THE CAUSE

e NO MATERIAL, CHEMISTRY, OR OTHER ABNORRITIES WERE RCL'ND c

l 0 CHECK VALVE, ELBCW, AND PIPING WERE REPLACED, AND THE PLANT RETURNED TO POWER i

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Sketch of the Cracking in the Tihange 1 Safety Injection Piping System e

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PIPING SYSTEM REVIEW 8 OBJECTIVE e SELECTION CRITERIA 8 REstLTS

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OBJECTIVE IDENTIFY SYSTEMS MOST LIKELY TO EXPERIENCE THERfML STRATIFICATION IDENTIFY TEhPERATURES OF HEAT SOURCES WITHIN THE SYSTE65

o CRITERI A FOR IDENTIFY.lflG,UNlSCLABLE PIEEt SEC.T.LQtG PIPE SECTIONS BETWEEN RCS AND FIRST CHECK VALVE SECONDARY SIDE OF CHECK VALVE PAY EXPERIENCE PRESSURES HIGHER THM' RCS PRESSURE IF ISCLATION VALVE LEAKS IF IN-LEAKAGE OCCURS, TEMPERATURE OF LEAKAGE COULD CAUSE

• THERMAL STRATIFICATION IN UNISCLABLE PIPING

s RESLLTS 0F PIPlNG SySTQi.BEVIERS NINE PlPINs SECTIONS WERE IDENTIFED AS "UNISOLABLE":

4 SAFETY INJECT 10N LINES ATTACHED TO COLD LEG (LOOPS A, B, a C) e SAFF.1Y INJECTION L INES ATTACHED TO HOT LEG (LOOPS A, B, a C) e NORf&4 CHAMiNG LINE 8 ALTERNATE CHARGING LINE e AUXILIARY PRESSURIZER SPRAY LINd

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POTENTIAL INSPECTION LOCATIONS 0 STRATIFICATION SCENARIO ,

9 -CRITERIA FOR INSPECT 10N LOCATIONS

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STRATIFICATION SCENARIO

-0 iSOLAT10N VALVE LEAKS FLOW G PRESSURE BUILDS UP BEHIND CHECK VALVE (P2 )

e hHEN PRESSURE EXCEEDS LOOP PRESSURE (P2 > P j), CHECK VALVE OPENS 8 SMALL AMOUNT OF WATER ESCAPES, LEADING TO POTENTIAL STRATIFICATION J

e AFTER PRESSURE EQUALIZES, CHECK VALVE CLOSES AGAIN, AND THE CYCLE REPEATS Y

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CRITERIA FOR INSPECTION LOCATIONS 0 EXPERIENCE WITH EARLIER FAILURES j 0 POTENTIAL FOR HIGH DELTA T 8 DISCONTINUITIES IN PIPING i

3 .e PR10RITIZAT10N OF INSPECT 10N LOCATIONS 0

0 OBJECTIVE F

0 PRIORITIZATION CRITERIA 4

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OBJECTIV"1 PRIORITIZE LOCATIONS TO ENSURE COVERAGE OF MOST CRITICAL LOCATIONS  !

i WITHOUT AFFECTING PLANT SAFETY i i

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THIS CAN BE DONE BECAUSE THE KNOWN INCIDENTS OF CRACKING ARE IEW, I

AND IN EACH CASE LEAK-BEFORE-BREAK WAS DEMONSTRATED j-4

- MONITORING WILL DETERMINE WHETHER STRATIFICATION IS OCCURRING I

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j FACTORS USED TO PRIORITIZE INSPECTIONS 1

POSITIVE IN-SURGE PRESSURE AT CHECK VALVE

2. TEMPERATURE DIFFERENCE AT

3. LOCAL GE0ETRY

4 INDUSTRY HISTORY OF CRACKING

5. PLANT AGE 4

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WESTINGHOUSE PROPRP/TARY TABLE 1 TEMPERATURE AND PRESSURE DIFFERENCES A$ A BASIS FOR PRIORITIZATION r.

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waarusonouse enornceTAQv TABLE 2 PRIORITIZATION OF PIPING SYSTEMS FOR INSPECTION CONSIDERATIONS

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INSERVTCE INSPECTION LOCATIONS RESULTS FROM PRIORITIZATION j

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Picino System Number of locations t

1 Loop C hot leg SI 4 2 Loop A cold leg SI 5 L p B het leg SI 3 1 4 Loop B cold leg SI 1 .

5 Loop A het leg SI 1 6 Loop C cold leg SI 1 .

7 Auxiliary Spray (3 are PT, 1 is UT)  !

8 Normal Charging 1 9 Alternating Charging j TOTAL 19 (16 UT) l t

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PROPRIETARY INFORMATI0ft REMOVED i

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. Locations for Inservice Inspection and Monitoring on the Unisolable Section of the Loop C Hot Leg Safety injection Line wwwnee se d 4

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- WESTINOMOUS: PROPRetTARY 1

PROPRIETARY INFORMATION REMOVED l

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4 f0NITORING PLAN 8 OBJECTIVE e SELECTION CRITERIA e RESULTS

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u CRITERIA FOR SFLFCTING MONITORING LOCATIONS BASED ON HEAT TRANSFER, SELECT THE LOCATION THAT WILL EXPERIENCE THE HIGHEST AT IF THERMAL STRATIFICATION OR CYCLING EXIST FARLEY AND TIHANGE EXPERlENCE

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i PROPRIETARY IfiFORitATI0t1 REMOVED Mounting Locations for Temperature Sensors w s. a s m ,e

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GUlDELINES FOR INSERVICE INSPECT 10N 0 NDE APPROACH 0 ACCEPTANCE CRITERIA

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0 600 REFRACTED SHEAR WAVE, G 1.5 WZ l i

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8 TRANSDUCERS 0.25 - 0.5 INCH DIAETER i f

8 SENSITIVITIES AT 14 DB ABOVE REF. SENSITIVITY  !

8 NOISE LEVEL LESS THAN 10% FULL SCREEN HEIGHT -

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FLM EVALUATION (IF NEEDED) WILL FOLLOW GUIDELINES OF IWB  !

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SUMMARY

AND CONCLUSIONS 8 DETAILED REVIEW PERFORhED ON V. C SUb?tR PIPING SYSTEMS 8

THIS REVIEW INCLUDED FLUID SYSTEMS STUDY AND EXPERIENCE WITH PREVIOUS FIELD FAILURES 4 19 LOCATIONS CHOSEN FOR INSPECTION 8 9 LOCAlIONS CHOSEN FOR MDNITORING 8 ANY INDICATIONS FOUND WILL BE SUBJECTED TO EVALUAT10N USING ASSE SECTION XI AS A GUIDELINE 8 THIS APPROACH PROVIDES THE OPTlh0M C0hBINATION OF INSPECTION EFFlCIENCY AND VERIFiCAT10N OF THE INTEGRlTY OF THE LINES OF INTEREST