ML20056A884

Responds to NRC Forwarding Insp Repts 50-206/90-10,50-361/90-10 & 50-362/90-10.Results of Review of Awareness & Response to Industry Check Valve Concerns & Evaluation of Need to Establish Dedicated Program Provided

ML20056A884
Person / Time
Site:	San Onofre
Issue date:	06/25/1990
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20056A882	List: IR 05000206/1990010 ML20056A884
References
NUDOCS 9008090383
Download: ML20056A884 (17)

Text

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REGl0lly ms Southem Calihmia Edison Compaqn ytm yg jy; g,35 1

23 PARKER STREET l

1RVINE, CAL.f rOONIA 9X788 HAROLD B. ' RAY T E L t. MON E June 25, 1990

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Mr. Dennis F. Kirsch, Chief Reactor Safety Branch

- U. S.

Nuclear. Regulatory Commission, Region V 1450LMaria Lane, Suite 210

. Wa) nut Creek, California 94596

Subject:

. Docket Nos. 50-206, 50-361 and 50-362 current-Check: Valve Program Activities

-San Onofre Nr. clear Generatina Station, Units 1.

2 and 3 Your letter dated May 18, 1990 forwarded NRC Inspection i

Report No. 90-10 which documents a routine unannounced inspection conducted at San Onofre by Mr. Clark.

The report discusses our current check valve program activities and includes the following

-among the-General Conclusions'and Specific Findings:

"The licensee has not est'ablished a specific check valve program to. address the latest check valve concerns in the industry."

Although-the report and your letter do not identify this as 1

an-item of NRC concern, Edison is concerned if the lack of such a

~

L specific program could adversely affect plant safety.. -Therefore, L

we have conducted a thorough-review'of our awareness and response l

to-industry check valve concerns and have made an evaluation of the need to establish a dedicated program specific to check

.va ves.

The purpose of this letter is-to describe the results of l

l that review and evaluation.

L

- Nuclear Industry Check Valve Group (NIC) j Edison is a longstanding, active member of NIC and chairs

. one of the subcommittees of its Check Valve Applications and i

Maintenance Committee (CAMP).

(NIC membership includes over two-J"

' thirds of all U.S.

nuclear utilities, and NIC was formally L%

acknowledged by the NRC Office of Nuclear Reactor Regulation in December 1989.)

We believe we are aware of current industry

. developments.with respect to identification and response to check i

- valve. concerns, however we are reviewing the subject again to verify this conclusion.

9008090383 900716 o

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~ Mr.. Dennis-.F. Kirsch WCd June 25, 1990 w

The inspection report included the finding that:

"The licensee has'not implemented any new procedures or programs since 1987, to address the current ~ check valve concerns raised in the-industry.,The licensee considered j

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that their existing valve programs (IST, etc.) were acceptable, and identitled-that they were informally following current check valve concerns."

' As indicated above, tie bel:. eve we are following these concerns effectively.

In discunsion with your office, we understand the-reference to'ourcent check valve concerns to be related to a monograph document issued by EPRI in 1988 entitle'

" Application Guidelines for Check Velves-in Nuclear Power l

Plants".

Although Edison'is not' currently a member of EPRI, we have reviewed the document and are.awate of'its status in the industry in general.

EPRI Guideline Doc'1 ment The stated objectives of the document are:

l

- o GN) assist utilities in developing programs in response to INPOLSignificant OperatingLExperience Report (SOER) 86-3.

o

'To provide technical guidance for preventing premature valve failure-and'for assessing'long-term reliability of existing j

check valve installations.

Edison's; response to'SOER'86-3 has twice'been evaluated by

~INPO.

In 1989'INPO determined that Edison had fully. implemented its guidance.

This determination was recently confirmed as part

.)

of:our review:in response to Inspection Report No. 90-10.

In addition, in 1989 INPO issued Significant Event Report 89-023, " Check Valve Failures".

INPO SER 89-028-This SER discusses continuing significant events involving

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-check valve failures.

It states that it is important to fully implement SOER 86-3 and to:

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Evaluate similar check valves when a deficiency is identified in a check valve.

o Use maintenance history-when selecting check valves for 3

inspection and' analysis.

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v ymg Mr. Dennis F. Kirsch

. -[- 3P" June 25, 1990 o

Provide adequate details for the maintenance, inspection and testing of check valves.

In an report dated April-30, 1990, Edison documented its evaluation of SER 89-028 and concluded'that its recommendations, and those of SOER 86-3,-were fully implemented.

Therefore, Edison has recently and formally evaluated its response to the current industry concerns identified by INPO.

Recent Industry Developments Enclosed for your information is a copy of a recent summary paper entitled " Industry Efforts to Increase Check Valve Reliability", which was presented by the chairman of NIC.

Edison o

is following, and participating in, these efforts.

Mith respect to the 1988 EPRI document discussed above, the:

j paper notes that one of the CAMP committees has it under

-j evaluation and that:

"This committee will identify the strengths and weaknesses of this document and make recommendations to revise its 4

content."

.y In other words, the EPRI document is not accepted by the industry.as a description of its current concerns and the means by which they should be addressed.

To the contrary, it is viewed as requiring extensive revision prior to being used as industry guidance.

The summary paper also discusses activities related to-further addressing check valve reliability and integrity in the ASME Code.- Edison believes the Code, as implemented by paragraph 50.55a(g) of 10 CFR Part 50, is the appropriate forum in which this development should occur.

lt Establishment of a SDecific Check Valve Procram 4

As summarized above, our review in the wake of the comments c

in_T.nspection Report No. 90-10 indicates that Edison continues to g"

address what we recognize as the latest check valve concerns in

.the industry..However, we also conclude that it would be L

appropriate and beneficial to establish a formal program to provide coherence'and visibility to our activities.

This program o

will be' managed by engineering personnel at'the Station and o'^

includeLengineering and technical personnel from the design and y

quality organizations.

Program documentation will be complete t/

October 1,7 1990.

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. Mr. Dennis-F.fKirsch

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June 25,fl990

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I If you have any questions or comments concerning the above,

. or.if you would like add'cional information,:please let me know, i

Sincerely,

/

. Encicsure j

cc:

Mr.' John:B.' Martin, USNRC,. Region V Mr.' C. W.,Caldwell, Senior Resident Inspector, San Onofre

' Mr. J. E. Tatum, NRR SONGS.1 Proj ect Manager g 'b

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e lNDUSTRY. EFFORTS TO INCREASE s

CHECK VALVE RELIABILITY.

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TECHNICAL SUPPORT WORKSHOP

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ATLANTA, GEORGIA MAY 9-11, 1990

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4 HICHAEL T. ROBINSON a

h CHAIRMAN, NUCLEAR INDUSTRY CHECK VALVE GROUP i

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INTRODUCTION AND BACKGROUND-

- THE-NUCLEAR REGULATORY COMMISSION (NRC) CONTACTED OWNERS GROUPS URGING THEM'TO. ADDRESS THE PROBLEMS ASSOCIATED WITH THE DESIGN, TESTING, AND MAINTENANCE OF CHEvn "",VES.

'kr SUBSEQUENTLY, INPO ISSUED SIGNIFICANT OPERATING EVENT j

REPORT 86-03, " CHECK VALVE FAILURES OR DEGRADATION."' -IHE UTILITY

- 0WNERS GROUPS MET AND FORMED THE OWNERS GPOUPS IASK L

TO DIVELOP APPLICATION GUIDELINES FOR CHECK VALVES.

THE Gul'JELINES WERE WRITTEN BY: MPR ASSOCIATES AND KALSI ENGINEE UNDER CONTRACT WITH THE ELECTRIC POWER RESEARCH INST HANY UTILITIES HAD CHECK VALVE PROGRAMS UNDER DEVELOPMENT BY 1990.

MOST OF THESE PROGRAMS !NCLUDED:

b 1). DESIGN REVIEWS & EVALUATIONS 2)

WALKDOWNS FOR INTERFERENCES ~

i 3)

PERIODIC TESTING 4)

.ALVE DISASSEMBLY CHECK VALVE DISASSEMBLY IS PRESENTLY BEING PERFORMED WHERE

~ TESTING TO VERIFY CHECK VALVE INTEGRITY 15 NOT AVAILABLE.

BECAUSE OF ALARA CONCERNS, THE LESS-THAN-ADEQUATE INDICATION OF VALVE-INTEGRITY, AND THE INADEQUATE INDICATION OF VALVE,

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I PERFORMANCE WHEN DISASSEMBLY IS USED IN PLACE OF TESTING, MANY.

UTILITIES ARE LOOKING FOR ALTERNATE METHODS.

1 UTILITIES HAVE ATTEMPTED'TO OBTAIN THE " MAXIMUM-WEAR TOLERANCES" FROM VALVE SUPPLIERS.

MANUFACTURER'S INFORMATION IS NORMALLY BASED ON VALVE DESIGN REQUIREMENTS, NOT THE PREDICTED POINT OF t

FAILURE.

SOME' MANUFACTURERS WILL GIVE THE MINIMUM DESIGN DIMENSIONS AND TOLERANCES UPON REQUEST, BUT.THIS INFORMATION IS L

NOT READILY AVAILABLE.-

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IHE INDUSTRY NEEDED TO LOOK FURTHER.

SOME DIAGNOSTIC VENDORS ARE t

. USING-NON-!NTRUSIVE DIAGNOSTIC METHODS TO DETERMINE CHECK. VALVE INTEGRITY.- IHOUGH METHODS ARE1AVAILABLE, MOST' UTILITIES ARE NOT READY.TO COMMIT TO THEIR USE UNTIL THEY HAVE BEEN PROVEN IN CHECK YALVE APPLICATIONS.

J iI THE lNDUSTRY COMMITMENT 1

' lN! JANUARY.1989, APPROXIMATELY 20 UTILITIES MET AT THE EPRI'M8D v

CENTER ATLEDDISTONE, PENNSYLVANIA, TO DISCUSS CHECK VALVE PROGRAMS AND NON-INTRUS!VE f5 STING TECHNIQUES AVAILABLE.

THE l l CONCLUSIONS MADE AT THIS M:GTING WERE:

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BETTER COOPERATION AND COMMUNICATIONS AMONG UTILITIES,

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NRC, INPO, AND OTHER ORGANIZATIONS SUPPORTING THE INDUSTRY IS NEEDED TO RESOLVE CHECK VALVE CONCERNS.

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2 )'- NON-INTRUSIVE TESTING TECHNIQUES NEED MORE RESEARCH AND

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-DEVELOPMENT TO VERIFY THEIR-CAPABILITIES PRIOR TO lNDUSTRY USE.

UTILITIES PRESENT ORGANilED A COMMITTEE TO DEVELOP A CHARTER FOR

'THE FORMATION OF.A UTILITY GROUP.TO RESOLVE CHECK'YALVE ISSUES.

T

!DURING FEBRUARY AND MARCH OF 1989,'SEVEN UTILITIES MET TO DEVELOP

~A CHARTER FOR-THE NUCLEAR INDUSTRY CHECK VALVE GROUP, NIC.

PER THE CHARTER,- ANY UTILITY MAYLBE A MEMBER, EACH MEMBER UTILITY l

SHALL'HAVE-ONEtVOTE, AND 1T IS NOT A REQUIREMENT FOR MEMBERSHIP Il TO-PARTICIPATE IN' FUNDING; HOWEVER, PARTICIPAT10N IN FUNDING.MAY t-

-BE A PREREQUISITE'FOR THE UTILIZATION OF INFORMATION DERIVED FROM J

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.TNE ACTIVITY.

THOUGH ONLY-UTILITIES CAN BE MEMBERS.0F NIC,

<0UTSIDE:0RGANIZATIONS,ARE' ENCOURAGED'TO-PARTICIPATE IN NIC

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li ACT IV I T_I ES.

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NIC 0BJECTIVES:-

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PROVIDE A-FORUM FOR THE DISCUSSION AND RESOLUTION OF GENERIC CHECK YALVE ISSUES THROUGH COMMUNICATION BETWEEN MEMBERS AND'0THER ORGANIZATIONS.

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PROVIDE A MECHANISM FOR MAKING RECOMMENDATIONS ON GENERIC CHECK VALVE ISSUES.

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PROVIDELAN EFFECTIVE NETWORK FOR-COMMUNICATING ON CHECK VALVE ISSUES WITH INP0,:NUMARC,- ASME, AND OTHER INDUSTRY

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ORGANIZATIONS.

4)

IMPROVE' PLANT SAFETY AND AVAILABILITY THROUGH-RECOMMENDATIONS OF PROGRAMS WHICH ADDRESS GENERIC ISSUES'.

THE NUCLEAR INDUSTRY CHECK VALVE GROUP (NIC)

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' iTWENTY-SEVEN UTILITIES' MET IN' BALTIMORE, MARYLAND, ON APRIL 19-AND 20 1989, TO APPROVE THE NIC CHARTER,-STEERING COMMITTEE, AND

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FOUR: WORKING : COMMITTEES.

SINCE THE APRIL MEETING, NIC uAs EVJLVED TO A WELL-RESPECTED UTILITY ORGANIZATION MEETING AT LEAST THREE TIMES A YEAR.

TECHNICAL INFORMATION COMMITTEE (IIC)

IHE TECHNICAL INFORMATION COMMITTEE IS TO ESTABLISH A-MECHANISM a

.FOR THE IDENTIF.! CATION AND RETENTION OF INFORMATION WHICH CAN BE

'USED-BY UTILITIES TO' IMPROVE CHECK VALVE RELIABILITY.

SPECIFIC

' FUNCTIONS OF IIC11NCLUDE:

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COLLECTING INFORMATION FROM NIC MEMBERS, OTHER UTILITIES, AND YENDORS 0. VERIFYING INFORMATION 15 AP!'ROPRI ATE a

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0-~ ' ENSURING INFORMATION IS 'BEING STORED: USING A METHOD WHICH.

IS.U3ABLE'BY'ALL NIC MEMBERS J.

0 ' PERIODICALLY UPPATE'AND PROVIDE COPIES OF THE DATA BASE'TO t

ALL NIC MEMBERS 7

o 0-ESTABLISH AND MAINTAIN AN NIC TECHNICAL LIBRARY

'PRESENTL",;IIC IS GATHERING INFORMATION FROM NIC MEMBERS AND OTHER. ORGANIZATIONS AND IS ESTABLISHING A DATA BASE AND TECHNICAL LIBRARY.

CODE' COMPLIANCE COMMITTEE-(CCC)

.THE CODE COMPLIANCE. COMMITTEE WAS ESTABLISHED'TO MONITOR REGULATORY AND INDUSTRIAL REQUIREMENTS AND GUIDELINES WHICH APPLY I

TO' CHECK VALVES.

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PRESENTLY THERE IS ONLY ONE SPECIAL WORKING GROUP UNDER THE CCC, LAND THIS' WORKING GROUP. REPORTS DIRECTLY TO THE NIC STEERING COMMITTEE.

THISGROUPISWORKINGWITHTHEASMEOMC6kMITTEEON-O DEVELOPING OM-22, " PERFORMANCE IESTiriG OF CHECK VALVES IN LWR POWER PLANTS."

NIC PRESENTLY HAS 33 19TERESTED NIC PERSONNEL s.

INYOLVED:WITH THIS EFFORT.

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CNECK VALVE' APPLICATIONS AND MAINTENANCE COMMITTEE (CAMP)

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IHE CHECK VALVE APPLICATIONS AND MAINTENANCE COMMITTEE MONITORS I

PRACTICES OF NIC MEMBERS.ON DESIGN APPLICATIONS, MAINTENANCE, ENGINEERING, PROGRAM EFFECTIVENESS, AND-TESTING.

EFFORTS-0F CAMP INCLUDE GETTING VENDORS MORE INVOLVED WITH CHECK VALVE PROBLEMS, SURVEYING UTILTTY PROGRAMS, SUMMARIZING INP0/NRC EVALUATIONS, AND-i

'PROVIDING GOOD PRACTICES IN THE AREAS OF MAINTENANCE AND TESTING.

PRESENTLY THERE ARE FOUR CAMP WORKING COMMITTEES:

J' HAINTENANCE PRACTICES WORKING COMMITTEE IS PRESENTLY WORKING ON INSPECTION GUIDELINES FOR CHECK VALVES.

2)

BULLETIN WORKING COMMITTEE.WILL PROVIDE PERIODIC CHECK VALVE INFORMATION TO NIC MEMBERS ON A SCHEDULED FREQUENCY.

3)

EPRI/INP0 GUIDELINES WORKING COMMITTEE IS EVALUATING THE EPRI " CHECK VALVE APPLICATIONS GUIDELINES'."

THIS COMMITTEE WILL IDENTIFY THE STRENGTHS AND WEAKNESSES OF THIS-DOCUMENT AND MAKE RECOMMENDATIONS TO REVISE ITS CONTENT.

4)

ASME SECTION-XI/GL 89-04,. RELIEF REQUEST GENERIC L

GUIDELINES WORKING COMMITTEE IS DEVELOPING GUIDELINES FOR A RELIEF REQUEST BASED ON ACTUAL MAINTENANCE HISTORY OR ALTERNATE TESTING METHODS.

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n lNON-INTRUSIVEExAMINATIONOFCHECKVALvESCOMMITTEE(NEC

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EXAMINATION OF CHECK VALVES.COMMITTEEflS T0-ESTABLISH _AND' PROVIDE A FORUM FOR THE IDENT.lFICATION AND 1

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' EVALUATION 0F.YARIOUS METHODSLOF NON-INTRUSIVE EXAMINATION"0F-1 f

CHECK' VALVES.<

t IN APRIL 1989,LTHE NEC INIT-!ATED YARIOUS TASKS FOR THE EVALUATION,

- OF NON-INTRUSIVE EXAMINATION TECHNIQUES OF CHECK YALVES.

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~TASKSEINCLUDE:

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i TASK 1) -MADE INQUIRIES OF VARIOUS VENDORS REQUESTING THEM TO:!DENTIFY CLA1MS, BOTH CAPABILITIES'AND LIMITATIONS,-OF THEIR TECHNIQUES.

VENDOR INPUT WAS RECEIVED AND REVIEWED BY NEC'IN MAY 1989.

FROM~

f THESE INQUIRIES THE-FOLLOWING TECHNIQUES WERE y

H IDENTIFIED:.

,-(.'

i A)~ -ULTRASONICS B)- ACOUSTICS C)

MAGNETICS D)

RADIOGRAPH'.'

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TASK 2)

DEVELOPED't TEST PLAN TO DEMONSTRATE AND EVALUATE THE CAPABILITIES OF THE TECHNIQUES ON A TEST FLOW LOOP.

THE TEST PLAN WAS DIVIDED INTO THREE PHASES:

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' PHASE 1) ~ DEMONSTRATE 1 TECHNIQUES ON VALVES USED11N WATER:SYSTFMS (1.E.

FEED WATER, l

a COMPONENT COOLING, SAFETY INJECTION, n

a ETC.).

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PHASE 2). DEMONSTRATE TECHNIQUES ON VALVES-USED-IN-STEAM APPLICATIONS'(I.E., MAIN STEAL FAUX-STEAM, ETC.).

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' PHASE 3)

. DEMONSTRATE TECHNIQUES ON VALVES USED IN

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' AIR / GAS SYSTEMS (1.E., INSTRUMENT: AIR, b

PLANT AIR, ETC.).

IASK~3)- DEVELOPED REQUEST FOR 0UOTE-(RF0) FOR-APPROVAL FOR 7

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PHASE 1 DESCRIBED ABOVE.

-IASK4) l'SSUED'THE RFQ FOR BID'AND SELECTED A CONTRACTOR TO PERFORMETHE-TESTING.

4 IASK 5)

PERFORMED PHASE 1 TESTING.

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IASK 6)

COLLECT AND EVALUATE DATA FROM PHASE 1 TESTING-l-

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IASK 7.)

ISSUE REPORT THROUGH THE NIC STEERING COMMITTEE ON g

THE CAPABILITIES OF METHODS TESTED ih PHASE 1.

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PRESENTLY PH'ASE 1 TESTING'IS COMPLETE.- THE' FINAL.N!C REPORT;IS SCHEDULED-TO BE AVAILABLE To PARTICIPATING UTILITIES' AROUND THE-

'END OF' JUNE:1990, L

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y UPDATE

SUMMARY

OF PHASE 1

-p yT CHECK VALVES APPLIED IN WATER, APPLICATIONS IN THE-' SUMMER OF.1989, A TEST. PLAN WAS DEVELOPED FOR'THE: PHASE 1 TESTING T0 BE PERF0'RMED BY NEC.

THE TEST PLAN COVERS-A WIDE l.

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RANGE OF CHECK VALV2 TYPE / SIZES, MATE. RIALS, INDUCED VALVE 1

DEGENERATIONS, FLOW-CONDITIONS, AND DIAGNOSTIC TECHNIQUES.

'IHE VA'LVES TESTED.!NCLUDED:

10" CRANE CS SWING CHECK-VALVE 12" VAL-MATIC CS TILTING DISC CHECK VALVE f

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4" VELAN CS SWING. CHECK-VALVE 1

10" MISSION CS Du0, i

n li 10" VELANICS SWING CHECK VALVE k

16" ROCKWELL'CS TILTING DISC CHECK VALVE 4

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24" VAL-MATIC CS TILTING DISC CHECK VALVE L

20"'A8M-CS SWING CHECK VALVE I

'24" A&M CS SWING CH'ECK VALVE 6" POWELL SS SWING CHECK VALVE L

6" CRANE CS TILTING DISC CHECK VALVE i

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.x VALVE-IEST:.CONDIT'10NS INCLUDED:-

c NO DEGRADATION "NEW"'

lNDUCED SEAT LEAKAGE.

I 15% '& 30% HINGE PIN [I AMETER REDUCTION E

15% & 30% DISC STUD DIAMETER REDUCTION.

-BROKEN SPRING"(VALVES-WITH SPRINGS)

' DISC STUCK OPEN COMBINATIONS OF-THE ABOVE DEGRADATIONS f

MISSING DISC-u

' FLOW CONDITIONS:

ZERO FLOW BACK SEAT-IAPPING WITH & WITHOUT CAVITATION TWO MID-STROKE FLOW. CONDITIONS' l-SEAT IAPPING

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PUMP START & IRIP l

. REVERSE FLOW L

max! mum FLOW MINIMUM FLOW TO OPEN l'

.IHE' TEST PLAN WAS SENT TO SEVEN FLOW LOOP VENDORS.

THE RFQ u

L REQUESTED THE FOLLOWING FLOW LOOP CAPABILITIES:

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'A). : PHYS! CAL-REQUIREMENTST-PROVIDE STRAIGHT ^ RUNS 0F P! PING.-

BE ABLE TO. CHANGE OUT-L

-l VALVES-QUICKLY.

g B)

_ PLOW REQUIREMENTS -

PROVIDE FLOW. RATE TO 20,000 GPM.

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BE ABLE TO MONITOR AND' CONTROL THE FLOW RATE.

p C). PRESSURE AND IEMPERATURE REQUIREMENTS -

PRESSURES UP TO 200 PSIG.

j TEMPERATURE RANGING FROM 40 TO 100 DEGREES F.

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IURBULENCE GENERATION REQUIREMENTS -

CAPABLE TO REPEAT INDUCED-FLOW CONDITIONS.

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BACK' FLOW REQUIREMENTS -

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BE ABLE TO PROVIDE D/P ACROSS VALVE WHILE MONITORING MINOR BACK LEAKAGE.-

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.F)' PROVIDE.' INSTRUMENTATION AND CONTINUOUSLY RECORD THE FLOW l-

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LOOP PARAMETERS.

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UTAH: STATE UNIVERSITY WAS SELECTED TO PERFORM THE TESTING WHICH-

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' STARTED ON JANUARY 29. 1990, AND WAS COMPLETED ON MARCH 14, 1990, l

.THREE' DAYS AHEAD OF SCHEDULE.

ONLY ACOUSTIC, MAGNETICS, AND l::

-ULTRASONICS TECHNIQUES WERE TESTED BECAUSE RADIOGRAPHY PERMITS

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COULD NOT BE 0BTAINED.

RADIOGRAPHY WILL BE TESTED AT A NUCLEAR o

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s SITE IN'THE NEAR FUTURE.

THE PRELIMINARY RESULTS FROM'ALL THREE:

OF'THE DIAGNOSTIC TECHNIQUES ARE PROMISING.

EACHLTECHN!QUE'S ABILITY'WILL BE PRESENTED IN THE FINAL NIC REPORT.

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SUMMARY

OF NIC t

- NIC IS WELL REPRESENTED.

MEMBERSHIP INCLUDES OVER TWO-THIRDS OF ALL U.S. NUCLEAR UTILITIES.

THERE IS ONE FOREIGN NUCLEAR' UTILITY MEMBER. AND MANY OTHERS HAVE REQUESTED INFORMATION ABOUT

-l N DECEMBER OF 1989. THE NRC 0FFICE OF NUCLEAR-REACTOR REGULATION 1

l FORMALLYLACKNOWLEDGE'THE FORMATION OF NIC.

NIC HAS GIVEN VARIOUS i

PhESENTATIONS AND HAS BEEN ACKNOWLEDGED BY VARIOUS OTHER'!NDUSTRY ORGANIZATIONS INCLUDING THE ASME, ACRS, NUMARC, ETC.

THE FORMATION AND EFFECTIVENESS OF NIC SHOWS THE UTILITIES ABILITY TO WORK TOGETHER FOR A COMMON" GOAL.

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