ML18038A399

Forwards Summary of 880426 Meeting Re Unit Torus Wall Thinning & Teledyne Engineering Svcs Rev 1 to TR-6801-2, Mark I Torus Shell & Vent Sys Thickness Requirements Nine Mile Point Unit 1 Nuclear Station, Per NRC 880504 Request

ML18038A399
Person / Time
Site:	Nine Mile Point
Issue date:	05/27/1988
From:	Terry C NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18038A400	List: ML18038A399 ML18038A401
References
NMP1L-0260, NMP1L-260, NUDOCS 8806060222
Download: ML18038A399 (87)

Text

ACCELERATED D1SOGBUTJON DEMONST1I110N SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8806060222 DOC.DATE: 88/05/27 NOTARIZED-NO FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe AUTH.NAME AUTHOR AFFILIATION

'ERRY,C.D.

Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

DOCKET 05000220

SUBJECT:

Forwards summary of 880426 meeting 6 responds to 880504 ltr re torus wall thinning 6 Rev 1 to TR-6801-2,, "Mark I...."

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A001D COPIES RECEIVED:LTR ~ ENCL t

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EI T NIASA A A U MQHANK NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N.Y. 13212/TELEPHONE (315) 474.1511 j

May.27, 1988 NMPlL 0260 p

U.S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C. 20555 Re:

Nine Mile Point Unit 1

Docket No. 50-220 DPR-63 Gentlemen:

On April 26,

1988, Niagara Mohawk met with members of the Nuclear Regulatory Commission staff to provide information regarding the Nine Mile Point Unit 1

torus wal.l thinning.

Subsequent to that meeting, the Commission, in a May 4, 1988 letter, requested additional information (Attachment A, Item 4).

The attachments to this letter provide a summary of the April 26, 1988 meeting and respond to the requests in your May 4, 1988 letter, Very truly yours, NIAGARA MOHAWK POWER CORPORATION C.

D. Terry Vice President Nuclear Engineering and Licensing N3F/pns 5021G Attachments xc:

Regional Administrator, Region I Mr. R. A. Capra, Director Mr. R. A. Benedict, Project Manager Mr.

W. A. Cook, Resident Inspector Records Management 3806060222 380527 PDR ADOCK 05000220

. DCD.

P'

ATTACHMENT A Niagara Mohawk Power Corporation Summary of April 26, 1988 Meeting A presentation on torus wall thinning was given at an April 26, 1988 meeting with the Nuclear Regulatory Commission.

This presentation included a

discussion of past reports, investigations, inspection results and programs dating back to 1975.

A copy of the visual aids used during the presentation is included as Attachment B.

A comparison was made of the past inspection results to the most recent inspection results and the results taken in April 1988 at four additional locations.

The graphs depicting statistical analysis (reference Attachment D

Niagara Mohawk Calculation S22-4-WW198-STATOl) of past as well as current inspection results show that even for the worst case or limiting torus area (bottom), that the defined minimum general area wall thickness of 0.447 inches is not projected to be reached until 1992 or later.

Further, any local-areas falling below that minimum wall thickness of 0.447 inches can be analyzed per Teledyne Report TR-6801-2, Rev.

1 (Attachment C).

Graphs and several examples of how local areas falling below general area minimum wall can be analyzed were provided.

For example, a local area approximately 9 1/2 inches in diameter and approximately 30 mils deep (or 30 mils less than 0.447) is acceptable according to Teledyne Report TR-6801-2, Rev.

1.

The minimum wall thicknesses defined by Teledyne Report TR-6801-2 are based on meeting ASME Code allowables without regard to mill certification properties.

When the mill certification properties are accounted for, an additional margin of 27 mi ls could be justified.

Niagara Mohawk has positive mill certification identification of approximately 85-90 percent of the plate material composing the torus.

Operation until 1990 is justified based on the above discussion of existing margins.

To date, no credit has been taken for the additional margins relating to mill certification.

Our current long-term program includes investigation of possible modifications such as installation of saddles at mid-bay, oxygen control, cathode protection,

coatings, and increased surveillance of the torus.

The new program will provide for consistency on how measurements will be taken and their location.

This program will be in place by the end of July 1988, at which time we will inform you of the actions we plan to take.

The following questions were raised during the meeting:

1)

What affect does the sludge created by corrosion have on the ability of the Emergency Core Cooling Systems (ECCS) pumps to perform during a Loss of Coolant Accident?

5021G

C

Niagara Mohawk Calculation M79-81-M001 (Attachment E) addresses this concern.

This calculation shows that the specific gravity of a worst case slurry of water/sludge is 1.0058 and would:.not.,affect the function of the ECCS pumps.

An investigation of this matter also reveals no plugging of the core spray strainers or nozzles will result.

2)

Are there any plans to monitor the torus during mid-cycle?

Niagara Mohawk will take mid-cycle thickness measurements to confirm that the torus shell still meets required minimum wall thickness by June 30, 1989.

5021G

ATTACHMENT B Presentation Outline/Viewgraphs From

-April 26, 1988 Meeting In The Region I Office Regarding Torus Hall Thinning 5021G

NIAGARA hIOHANK POHER CORPORATION PRESENTATION TO HUCLEAR REGULATORY COllhlISSIOtl CONCERHING NINE NILE POIHT UNIT I IHSERVICE INSPECTION PROGRAhl AHO TORUS HOHITORING PROGRAH

AGENDA IHTRODUCTIOH - G, Gresock IHSERVICE INSPECTION OF HELDS AND SUPPORTS - T.

Lee TORUS MONITORING PROGRAM - R, Oleck REACTOR VESSEL BELT LINE IHSPECTIOH -

R. Pasternak EROSION/CORROSION PROGRAM -

R, Pasternak COHCLUDING REMARkS - C. Terry

IHTRODUCTION ROOT CAUSE ISI PROBLEIIS INADEQUATE MANAGEMENT ATTEHTION ROLES AHD RESPONSIBILITIES HOT CLEARLY DEFINED OVER RELIAHCE OH COHTRACTOR

SIPC

RESPONSE

TO PROBLEH TRAHSIiIOH PLAH DEFINE REQUIRED NORK FLOH CLEARLY DEFINE NHPC GROUPS RESPONSIBLE ASSURE iNAT PROCEDURES AND POLICIES HATCH DEFINED RESPOHSIBILITIES COHMITiED TO 100X OF FIRST AND SECOND INTERVAL REQUIREHEHTS BEFORE SiARTUP EXPAND STAFF TO ADDRESS ISI ISSUES

KEY TASKS FOR 1988 OUTAGE COMPLETIOH VERIFICATION OF PROGRAM PLAN REQUIREMENTS RESOLUTIOH OF HONCOHFORMANCES DETERMINATION OF EXPANDED INSPECTIOHS 1

SCHEDULIHG/TRACKIHG/MOHITORIHG INSPECTIONS

VERIFICATION OF 1ST AHD 2ND INTERVAL PROGRAM IDENTIFY COMMITTED INSPECTIONS (PROGRAM PLAH)

DEFINE LICEHSIHG REQUIREMENiS QUALITY ASSURANCE VERIFICATION OF IST INTERVAL IHSPECTIOHS COMPARE PROGRAM PLAN AND LICENSIHG REQUIREMEHTS COMPARE INSPECTIONS PERFORMED VERSUS PROGRAH PLAN

RESULTS OF 1ST INTERVAL VERIFICATIOHS REVIEH OF PROGRAH PLAN IH PROCESS INCLUDES REVIEH OF COMHITTED IHSPECTIOHS INCLUDES IDEHTIFYIHG CHANGES HADE LICENSING REQUIREMEHTS ARE IDENTIFIED 7242 DATA SHEETS EVALUAT":D BY QUALITY ASSURANCE APPROXIMATELY 700 BEIHG EVALUATED FURTHER 208 DCA PACKAGES BEIHG CLOSED OUT/SUMMAR!2ED COMPARISOH OF PROGRAM PLAN VERSUS LICEHSIHG REQUIREMEHTS-COMPLETE MAY 19 QUALITY ASSURANCE COHPARISON OF IHSPECTIOHS PERFORMED VERSUS PROGRAM PLAN IHITIAL VERIFICATION IS COMPLETE 700 - 1,200 UNRESOLVED ISSUES ADDITIONAL INSPECTIONS MAY BE REQUIRED FIHAL VERIFICATIOH TO OCCUR HHEH PROGRAM PLAH REVIEH COMPLETE

RESULTS OF 2HD IHTERVAL VERIFICATIOH AHII INITIALLYVERIFIED THE 1988 OUTAGE PLAH VERSUS THE ASME XI CODE REQUIREMEHTS 92 ADDITIONAL INSPECTIOHS IOEHTIFIED PLAN TO PERFORM 33'K OF PROGRAM PLAN REQUIRED INSPECTIONS RESOLVES AHII CONCERHS VERIFICATION OF 2ND IHTERVAL PROGRAM PLAN IH PROCESS-COI1PLETE MAY 19, 1988 INCLUDES QUALITY ASSURAHCE VERIFICATIOH OF IHSPECTIOH COMPARISON OF PROGRAM PLAN VERSUS LICENSING REQUIREMENTS COMPARISON OF IHSPECTIOHS PERFORMED VERSUS PROGRAM PLAI{

TORUS HALL THICKHESS PROGRAM I

HISTORY/BACKGROUND C.B.I, (1/16" CORROSIOH)

TORUS:

ISI 1975-1988 6x6 12xl2 MARK I PROGRAM 1975-1984 HATER QUALITY (IROiY-EATIHG BACTERIA) 1979/1980 RCT REPORT COHTAIHMEHT COATIHG STUDY 1984 1987 -

PART 21 - ENLUATIOH --)

NO CORROSIOH ALLOHAHCE --)

HO IMMEDIATE PROBLEM T,E.S, -->

REPORT 9/87 - 1/88 FURTHER TES EVALUATIONS - HELD REPAIR, PROPOSAL FOR LONG TERIA 2/5/88 1988 ISI/NRC READIHGS (UT)

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+-26.79

MARK I TORUS SHELL AHD VENT SYSTEH THICKNESS REQUIREHEHT TELEDYNE ENGIHEERIHG SERVICES REPORT TORUS SHELL ANALYSIS CALCULATIOH OF MINIHUH TORUS SHELL THICKNESS REQUIREIIENiS CALCULATIOH OF PERHISSIBLE LOCAL REDUCTIOH IH iORUS SHELL iHICKHESS FOR AN IHDICATION REVIEH OF CERTIFIED MATERIAL TEST REPORTS VEHT SYSTEM AHALYSIS CALCULATiOH OF MIHIMUM VENT SYSTEM THICKHESS REQUIREMEHTS CALCULATIOH OF PERMISSIBLE LOCAL REDUCTION IH VENT SYSTEH THICKNESS FOR AN IHDICATIOH

TORUS SHELL ANALYSIS HINIHUH TORUS SHELL THICKNESS RE UIREHEHTS THO CRITICAL TORUS SHELL AREAS HID-BAY BETHEEN RING GIRDERS TORUS SHELL ADJACENT TQ RING GIRDER CODE COMPLIANCE BASED OH COhIPARISON OF ACTUAL HARK I STRESS INTENSITY TO CODE ALLOWABLE STRESS

TORUS SHELL ANALYSIS TORUS SHELL STRESS REGIONS NINE NILE POINT UNIT I

NUCLEAR STATION I

t I

I I

t t

GtRDZR MID-BAY 8.SZ2S" 3.O37" S.6325 RIN tCK NESS G

GIRDER / MITRE MID-BAY THICKNESS

1

TORUS SHELL ANALYSIS MARK I PROGRAM EVENT COMBINATIONS 27 MARK I EVENT COMBIHATIOHS REDUCED TO 4

BOUHDIHG EVEHT COMBIHATIOHS BOUHDING EVENT COMBIHATIOHS NUMBER 14 TITLE C.O.,

Chug, O.B.E.,

S.B.A, S.R.V.

Pool Swell, O.B,E.,

D.B,A, C,O.,

Chug, O.B.E.,

D.B.A.

Pool Swell, S,S.E.,

D,B,A., S.R,V.

C.O.

Chug SBA DBA SRV OBE SSE CONDEHSATIOH OSCILLATIOH LOADS CHUGGING LOADS SHELL BREAK ACCIDENT (SHELL DIAMETER PIPE BREAK)

DESIGN BASIS ACCIDENT SAFETY RELIEF VALVE ACTUATIOH OPERATING BASIS EARTHQUAKE SAFE SHUTDOHN EARTHQUAKE

TORUS SHELL ANALYSIS MINIMUN SHELL THICKNESS NARK I PROGRAH LOADS PRESSURE LOADINGS HOOP STRESS - PRINARY STRESS BACK CALCULATE NININUN TORUS SHELL THICKNESS MID-BAY tFREE SHELL)

AREA ADJACENT TO RING GiRDER (LOCAL SHELL)

TORUS SHELL ANALYSIS TABLE 1

MINIMUM TORUS SHELL THICKNESS REQUIREMENTS NINE MILE POINT UNIT 1

NUCLEAR STATION Eiemen,t No.

(Midbay) 13 17 19 21 23 25 27 (Ring Girder) 123 129 135 141 147 153 159 Requi red Thickness (inches)

.304

.362

.418

.446

.447

.425

.382

.320

.287

.172

.191

.168

.173

.125

.139

.198 Remaining Thickness (inches)

.156

.098

.042

.014

.013

.035

.078

.140

.173

\\

.288

.269

.292

.287

.335

.321

.262 governs NOTE:

Only lower shell elements are listed.

TORUS SHELL ANALYSIS PERNISSIBLE CORRODED THICKNESS FOR THE TORUS CROSS-SECTION AT HID-BAY (FREE SHELL REGION)

NIHE NILE POINT UHIT I NUCLEAR STATION REACTOR ARC LENGTHS (INSIDE)

S9 156

.156 ~

S1=254.5 S2= 226.2 S3=169

~ 6 SO=113.1 S5= 56.

5'6=84.8'7=1

41. 4 S8=197.9 S9= 254.5

.173

.173

.098~

.04'2

.013

.035 NOTE:

INTERMED I ATE VAI l.]FR MAY BE I

BOTTOM

TORUS SHELL ANALYSIS PERHISSIBLE LOCAL REDUCTION IN TORUS SHELL TNICGESS FOR AN INDICATION ANALYTICAL BASIS EVALUATION OF CYLINDRICAL DEPRESSIOH EFFECTS ON LARGE CIRCULAR PLATE CONSTANT THICKNESS UHIFORM STRESS CALCULATIOH OF PERMISSIBLE LOCAL REDUCTIOH EQUIVALENT PRESSURE FOR A HOOP MEMBRANE STRESS EQUAL TO THE HARK I EVENT COMBINATION PRIMARY MEMBRANE (HID-BAY)

FOR LOCAL MEMBRANE (RIHG GIRDER REGIOH)

STRESS IHTEHSITY

TORUS SHELL ANALYSIS PERHISSIBLE SIZE RANGE FOR INDICATION FREE SHELL REGION OF THE TORUS NINE NILE POINT UNIT I

NUCLEAR STATION I

0,460" i3.0 12.0 11.0 10.0 9.0 823 ll 6,0 x

50 do 3,0 2,0 0.013'c-.0.173'RC REGION S1 S2 S3 S4 S5 S6

.S7 S8, S9 FACTOR I

0.800 0.851 0.930 0.974 1.000 1,000 0.965 0.904 0.824 GiN.

CGRR.

Cc 0.173 0.140 0.078 0.035 0,013 0.014 0.042 0.098 0.156 0.0 0.0 00 0.100 0.200 0.300 dtn) 0.400 0.460

TORUS SHELL ANALYSIS CERTIFIED MATERIAL TEST REPORT REVIEW FOR TORUS SHELL STATISTICAL AHALYSIS OF TORUS SHELL CERTIFIED MATERIAL TEST REPORTS LARGE SAMPLE 99% COHFIDENCE LEVEL FOR MATERIAL MINIMUM YIELD ULTIMATE STRENGTH CODE ALLOHABLE STRESS IHTEHSITY 16,500 PSI CALCULATE ALLOWABLE STRESS INTENSITY BASED ON CERTIFIED MATERIAL TEST REPORTS (2r) 17,600 PSI RESULT 6X ADDITIONAL MARGIH IH MINIMUM TORUS SHELL THICKNESS REQUIREMENTS

VENT SYSTEM ANALYSIS COMPONENT ANALYZED FOR STRESS VENT PIPE VEHT SPHERE VENT HEADER DOMNCOMERS CALCULATIOH OF MIHIMUM THICKHESS REQUIREMENTS TORUS SHELL METHODOLOGY PERMISSIBLE LOCAL REDUCTIOH IH VENT SYSTEM THICKNESS FOR AH INDICATION TORUS SHELL METHODOLOGY

VENT SYSTEN ANALYSIS TABLE 2 MINIMUM VENT SYSTEM THICKNESS REQUIREMENTS NINE MILE POINT UNIT 1 NUCLEAR STATION Component Location Vent Pipe Vent Header Downcomer Vent Pipe at 0rywe11 Vent Header at Mitre Joint Vent Header at Downcomer Downcomer at Mitre Joint Vent Sphere at t1 Vent Sphere-at t2 Vent Sphere at t3 She11 Thickness (in)

. 3125

.3125

.250

.3125

.3125

.3125

.250

.3125

.6875

.8125 ReqUired Thickness (fn)

.201

.159

.222

.134

.203

.248

.148

.290

.637

.753 Remaining Thickness (in)

.1115

.1535

.028

.1785

.1095

.0645

.102

.0225

.0505

.0595

VENT SYSTEN ANALYSIS VENT SPHERE LKAL THICKNESS REGIONS HIHE NILE POIHT UNIT I STATION VENT PIPE a=0.8125

.2=0.687=

'"'ENT HEADER TQP AND 30TTOH tj=0.3125 VENT HEADER tz =0.6875 4 =0.3125

VENT SYSTEH ANALYSIS PERHISSIBLE SIZE RANGE EOR INDICATIOH YENT SPHERE NINE NILE POINT UNIT I NUCLEAR STATION D'

I (t1, t2, t3) 10.0 90 B,O

.t c > =0.0225

tc a=D,0505' tc a=0.0595',0 6.0 5.0 4,0 C

3,0 2.0 1,0 0,0 0,000 0.000 0.000 I

I l

I l

I I

l l

I I

l I

I l

l l

l t3 0.0625 0.12 SO 0,1875 0.2S00 0.3125= t1 0 1375 0 27SO 04125 0 5S00 0 6875=t2 0.162 S 0.3250 0.4875 0.6500 0.8125= t3 cL'ln)

TORUS SHELL ANALYSIS ADDITIONAL MARGINS TO BE INVESTIGATED GOVERNING LOADS COHDEHSATIOH OSCILLATIOHS TORUS PRESSURE POTENTIAL REDUCTIONS IH MINIMUM TORUS SHELL THICKNESS COHDENSATIOH OSCILLATIONS 12 MILLS/10K REDUCTION TORUS PRESSURE 8 MILLS/1 PSI REDUCTION

EVENT 20 COMBINATION AT BOTTOM MID-BAY MINIHUH SHELL THICKNESS VERSUS P

STRESS AHD PERCENT DBACO LOAD 16025.

15596.

15167.

14738.

14309.

~~ 13880.

13451.

13232.

13022.

5 12593.

12164.

11735.

+

+

.369 IBACO STRESS 100 90 80 70 60 50 C>

40

'(

C) 30 20 10

.327

.351

.375

.399

.423

.447

.339

.363

.387

.411

.435 HININN SHELL THICKNESS (INCHES)

,0

EVENT ZO COHBINATION AT BOTTOH HID-BAY MINIMUM SHELL THICKNESS VERSUS P

STRESS AND HETHELL PRESSURE 16025.

15849, 15673.

15497.

15321.

15145.

14969.

}4793.

14617, 2

14441.

l4265.

t 26.0 I 25.5 t 25.0

24. 5 24.0 w

23.5 g 23.0 22,5

- 22.0 >

21.5 21.0

.398

,408

.418

.427

.437

.447

.403

.413

.422

.432

.442 MINING SHELL THICKNESS (INCHES)

k

CONSERVATISM IN VENT SPHERE MINIMUM THICKNESS LOADS HERE COMBINED BY ABSOLUTE SUMMATION RESULTANT STRESSES HERE CALCULATED HITHOUT REGARD TO LOCATION GENERAL ELECTRIC GEHERIC VEHT HEADER/VENT PIPE INTERSECTION CTYPE Ij STRESS IHTEHSITY EACTORS HERE USED TO DETERMIHE VEHT SPHERE MAXIMUM STRESS CMTRs COULD BE USED TO DETERMIHE HIGHER CODE ALLOHABLES

TORUS HALL THICKNESS PROGRAH II DATA COLLECTIOH METHODS

& EVALUATION UT METHOD/INSTRUMENT

- 1975-1979 -->

THICKNESS TRAHSDUCERS'SINGLE CALIBRATION BLOCK - 6x6 MIN, THICK.

STATISTICAL --->

TIHE VARYING LOCATION VARYIHG VENT HEADER SPHERES -->

HEH AREA, NO PREVIOUS DATA NO DETAILED STRESS AHALYSIS ANNUAL CORROSION (LINEAR/EXPONENTIAL>)

TORUS HALL THICKNESS PROGRAM III PRESENT PLANS/PROGRAMS CFOR 1990)

INCREASE SAMPLE SI?E/CONFIRM i988 DATA VISUAL INSPECTION VENT SPHERES FURTHER ANALYSIS FULL SCALE TEST DATA 02 CONTROL COATINGS MID-BAY SADDLES

0

TORUS HALL THICKNESS PROGRAH IV CONCLUSIONS HNY OK UNTIL 1990?

LOCAL THICKNESS VS.

OVERALL THICKNESS TORUS THICKNESS AT HID-BAY - ADJACENT CORROSION RATE -

.002 in/year VEHT SPHERE, THICKNESS - ADEQUATE CHTRs GIVE ADDITIONAL MARGIH FURTHER ANALYSIS TO INCREASE TNICKHESS HARGIH

.5000 NINE MlLE POINT UNIT IvI'INIMUM TORUS WALL THICKNESS AREA NUMBER ONE g

A4$ 1

.4575 RADIA AVG ANALYSIS LIMIt NRC STD

.4254 AIL GERT LIMIT 1 975 1 977 1 979 1 981 1 984 1 986 1 988 1 9SO 1 SS2 OUTAGE YEAR

RPV BELT LINE HELD EXAHINATIOH lST TEH YEAR INTERVAL RELIEF GRANTED DUE 70 ACCESS RESTRICTIONS 2ND TEN YEAR INTERVAL RELIEF REQUEST PEHDIHG NRR APPROVAL NIAGARA MOHAWK HILL EXAMINE THE RPV HELDS ABOVE THE THERMAL SHIELD l988 DETERMINE ACCESSIBILITY AHD IHSULATION MODIFICATIONS REQUIRED l990 TENTATIVE SCHEDULE FOR EXAMIHATIOH NRC INSPECTIOli 87-II NIAGARA MOHAHK COMMITTED TO PERFORM A FEASIBILITY STUDY OH RPV BELT LIHE EXAMINATIOHS

HMPC FEASIBILITY STUDY BHROG PLEX COMMITTEE PURSUING THIS TOPIC HITK EPRI/BHROG IGSCC DEVELOPIHG A SUBMERSIBLE UHIT FOR UT EXAMINATION FROM iNTERIOR COMBUSTION ENGINEERING LOH PROFILE MAGNETIC CRAHLER REQUIRES A THIH TRACK FOR ALIGNMENT INSULATION MODIFICATIONS REQUIRED SOUTHHEST RESEARCH LOH PROFILE DEVICE AVAILABLE USED ON EUROPEAH BHR TRACKLESS SYSTEM

EROSION/CORROSION MOHITORIHG PROGRAM IHITIAL PROGRAM DEVELOPMEHT IN,1981 FOR THO PHASE FLOH MONITORED THO PHASE FLOH LOCATIOHS DURING 1984 AND 1986 OUTAGES PROGRAM EXPAHOEO IH 1987 TO INCLUDE SIHGLE PHASE FLOH NUMARC/EPRI GUIOELIHES FOR HIGH-ENERGY SINGLE-PHASE FLOH EROSION/CORROSIOH REVIEH ARE IHCLUDED IN PROGRAM HRC BULLETIN HO.

87-01 GUIDELINES AHD RECOMMENDATIONS ARE INCLUDED IN PROGRAH

EROSION/CORROSION MONITORING PROGRAH (Continued)

PROGRAM TASKS DESIGN REVIEH PIPIHG COHFIGURATIOH BULK FLUID VELOCITIES HATER CHEHISTRY MATERIALS PERCENT MOISTURE IN STEAM FOR THO PHASE OPERATING DATA REVIEH TRANSIENT HISTORY HATER CHEMISTRY SAMPLE LOCATION

I988 REFUELING OUTAGE HIIPC PROGRAM PLAH NMPC OUTAGE PLAH CBI SURFACE PREPARATION HES ULTRASONIC MEASUREMENT HMPC EHGIHEERIHG REVIEH ACTUAL DATA VERSUS MINIMUM WALL THICKNESS REQUIREMENTS ACTUAL DATA INPUTTED TO "CHEC" COIIPUTER PROGRAM DEVELOPED BY EPRI MOHITORS EROSION/CORROSION RATE

NINE HILE POINT UNIT I

EROSION/CORROSION REVIEH STATUS PROGRAM LOCATIONS SINGLE PHASE THO PHASE DATA HES COMPLETED HES TO BE COMPLETED HES TURNOVER TO ENGIHEERING 37 NMPC EHGIHEERIHG DATA REVIEN COMPLETED

ATTACHMENT C Teledyne Engineering Services Technical Report TR-6801-2 Revision 1

January 29, 1988 Mark I Torus Shell and Vent System Thickness Requirements Nine Mile Point Unit 1 Nuclear Station 5021G

0