ML20031A220

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Slide Presentation Entitled Pressurized Thermal Shock of Pressure Vessels. Related Info Encl
ML20031A220
Person / Time
Issue date: 09/15/1981
From: Murley T
NRC
To:
Shared Package
ML20031A218 List:
References
REF-10CFR9.7 TAC-59974, TAC-59975, NUDOCS 8109220006
Download: ML20031A220 (62)
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PRESSURIZED lilERMAL bl10CK OF PRESSURE VESSEi.S j

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PRESSURIZED THERMAL SHOCK OF PRESSURE VESSELS COMMISSMN BRIEFING I.

SUMMARY

OF THE PROBLEM 11.

DISCUSSIONS WITH INDUSTRY III.

RECENT INFORMATION IV.

POSSIBLE REGULATORY LIMITS V.

STAFF CONCLUSIONS

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SUMMARY

OF THE PROBLEM i

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V RANCHO SECO 3-20-78 TRAMSIENT 2000 k N

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AUTOMATIC ACTION 500 0

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C 60 120 180 2:40 TIME, MIN.

w SI VESSEL WALL TEMPERATURE VS. TIME AND DEPTH 600 TIME, MIN, 10 500 -

400-30 p

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50 200 -

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STRESS DISTRIBUTION THERMAL STRESS

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MATERIAL

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IOUGHNESS

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'.'NIRRADI ATED I.

l RTNDTO TEMPERATURE

NEUTRON-RADIATION-INDUCED 4

TOUGHNESS CHANGES 1

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MATERIAL

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TOUGHNESS f

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4 TEMPERATURES DURING OPERATING TRANSIENT TEMPERATURES l

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MATERIAL y

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i II, DISCUSSIONS WITH INDUSTP.Y r

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DISCUSSIONS WITH IJDUSTRY GROUPS

-- MARCil 31, 1981, MEETING Wil!f PWR REGULATORY RESPONSE GROUPS

-- APRIL 29, 1981, PROGRESS BRIEFI'NG FROM PWR OWNERS GROUPS

-- MAY 15, 1981, REPORTS FROM OWNERS GROUPS

-- MAY 30, 1981, REPORTS FROM PWR' LICENSEES

-- JULY 28-30, 1981, MEETINGS WITil OWNERS 6R0 BPS

-- AUGuSr 21, 1981, LETTERS TO 8 LICENSEES

-- SCHEJULE FOR MEETINGS ON TECHNICAL ISSUES

-- W OWNERS GROUP - SEPTEMBER 18, 1981

-- BSW OWNERS GROUP - SEPTEMBER 22, 1981

-- CE OWNERS GROUP - OCTOBER 7, 1981

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PRELIMINARY STAFF CONCLUSIONS PRESENTED TO OWNERS GROUPS 1.

EFFORTS SHOULD CONTINUE TO REDUCE THE PROBABILITY AND SEVERITY OF OVERC00 LING TRANSIENTS 2.

RELIANCE ON THE dPERATOR ACTION TO PREVENT REPRESSURIZATION IS NOT AN 1

ACCEPTABLE LONG-TERM SOLUTION i

3.

A LIMIT SHOULD BE ESTABLISHED ON RTNDT FOR CONTINUED OPERATION

2 INDUSTRY VIEtiS -- BaW PLANTS

-- BOUNDING TRANSIENT IS SMALL BREAK LOCA

-- PRELIMINARY ANALYSIS USING REALISTIC ASSUMPTIONS SHOWED OCONEE-1 VESSEL COULD SUSTAIN THE SDLOCA AFTER 32 EFPY

-- ANALYSIS ASSUMES OPERATOR ACTION TO PREVENT REPRESSURIZATION

-- PLANT SPECIFIC ANALYSES PLANNED OCONEE 1 DECEMBER 31, 1981 RANCHO SECO flARCli 1,1982 OTHER PLANTS LATER IN 1982

1 i

Il1DUSTRY VIENS -- WESTIllG1100SE PLANTS BOUNDING TRANSIENT IS PLANT SPECIFIC (LARGE LOCA, SMALL LOCA OR STEAM LINE BREAK) r

-- ALL W PLANT.S CAN SAFELY SUSTAIN SEVERE T!!ERMAL Sil0CK TRANSIENT, INCLUDING REPRESSURIZATION, TO BEYOND JANUARY 1983 GENERIC ANALYSIS SCHEDULED FOR COMPLETION DECEMBER 31, 1981 i

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.o INDUSTRY VIEWS -- CE PLANTS

-- BOUl1DitlG TRANSIEllT IS A STEAM LillE BREAK

-- MOST LIMITING PLAi4T CAN SAFELY SUSTAlti Tile MOST SEVERE OVERC00 LING TRAllSIENT,FOR AN ADDITI0llAL 5 EFPY

-- ANALYSIS A$SUMES NO OPERATOR ACTI0ll BEYOND Tl10SE PRESCRIBED BY PROCEDURES

-- GENERIC ANALYSIS SC51EDULED FOR COMPLETION DECEMBER 31, 1981

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i Reference Temperature for the Reactor Vessels Owned by the Eight Recipients of the Aug. 21, 1981 Letter on Pressurized Thermal Shock Reference Temperature, Plant NSSS Vessel RTNDT, deg. F.

Vendor Fabricator Cir. Welds Lona. Weios Oconee 1 B&W B&W 150 170 Three Mile Is. 1 B&W B&W 180 160 Fort Calhoun CE CE 280 280 Maine Yankee CE CF 240 240 Calvert Cliffs 1 CE CE 230 230 Robinson 2 West.

CE 290 290 San Onnfra 1 West.

CE 270 270

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Turkey Point 4 West.

B&W 290 Forgings l

SUMMARY

OF INFORMATION REQUESTED FROM 8 LICENSEES 60 DAYS

-- RTilDT VALUES OF THE CRITICAL WELDS AND PLATES

-- RATE OF INCREASE OF RTilDT

-- APPROPRIATE, LIMIT ON RTilDT FOR CONTINUED OPERATION

-- OPERATOR ACTIONS TO PREVENT PRESSURIZED THERMAL SHOCK

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151LDAYS

-- PLAN FOR RESOLVING THE ISSUE

-- EVALUATION OF POSSIBLE CORRECTIVE ACTIONS

-- IMPLEMENTATION SCHEDULES

-- DETAILED INFORMATION FOR STAFF EVALUATIONS

III.

?.ECEni INFORMATIUd L.

RECENT INFORMATION

-- OCONEE-1 IN-SERVICE INSPECTION SHOWING INDICATIONS OF SMALL CRACKS UNDER THE CLADDING

-- OVERC00 LING TRANSIENTS AT BORSSELE AND SAN ONOFRE

-- SENSITIVITY CALCULA:TIONS BY STAFF

- RANCHO SECO TRAN,SIENT AS A BENCHMARK

- NOMINAL MATERIAL PROPERTIES

- VERY CONSERVATIVE PARAMETERS AND MATERIAL PROPERTIES I

LOVIISA 1 EXPERIENCE NONITORING PROGRAM SHOWED WFLD EMBRITTLEMENT FASTER THAN EXPECTED RT INCREASED FROM 450F TO 1820F~

I 36 0 UTER FUEL, ELEMENTS WERE REPLACED BY DUMMY ELEMENTS IIEUTRON FLUX AT VESSEL WALL REDUCED TO 1/3 ORIGINAL VALUE 0

TEMPERATURE OF ECC NATER FROM llPI RAISED FROM 68 F TO 113-131 F

BORSELLE EVENT - MARCH 2, 1981

-- 400 MWE, 2 LOOP, 2 S-G, KWU DESIGfl

-- O!' RING MAINTENANCE, SOME ELECTRICAL C0' NECTIONS AFFECTIflG SECONDARY N

SAFELY VALVES WERE INTERCHANGED

-- DURING STARTUP (fl0T CRITICAL) OPERATOR ' TESTED POWER TO A PILOT VALVE, CAUSING S-G SAFETY; VALVE TO OPEil

-- VALVE DID fl0T RECLO,SE (APPARENT INDEPENDENT FAILURE)

-- ONE S-G BOILED DRY, OPERATORS ISOLAT'dD SECOND S-G, TURNED ON CHARGING PUMPS TO REGAlti PRESSURIZER LEVEL

-- PRIMARY TEMPERATURE DECREASED FROM 446 F TO 284 F IN 20 MIN.

-- PRIMARY PRESSURE DROPPED TO 2130 PSIG, THEN IllCREASED TO 2350 PSIG BY CHARGING PUMPS 1

SAN ON0FRE FEEbWATER TRANSIENT - SPET. 3, 1981 POWER SUPPLY FAILURE CAUSED PARTIAL CONTROL SYSTEM FAILURE OSCILLATIONS OBSERVED IN FLOW AND LEVEL'0F STEAM GENERATORS OPERATORS TRIPPED THE REACTOR MANUALLY NATURA!. CIRCULATION WAS ESTABLISHED IN ACCORDANCE WITH PROCEDURES AFTER 8 MINUTES SAFETY INJECTION OCCURRED DUE TO LOW PRESSURE OPERATORS IMPLEMENTED Ti1E LOCA PROCEDURE UNTIL IT WAS ESTABLISilED TilAT A LOCA IIAD NOT OCCURRED COLD LEG TEMPERATURE DROPPED FROM 532 F 10 462 F IN 10 MINUTES NO DATA ON PRESSURE WAS RECORDED

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POSSIBLE REGULATORY LIMITS l

POSSIBLE CORRECTIVE ACTIONS 1

REDilCE Tile PROBABILITY OF OVERCOOLING TRANSIENTS (E.G., MORE REl.IABLE C0flTROL SYSTEM) 2.

REDUCE TllE SEVERITY OF OVERC00 LING TRANSIENTS (E.G., RAISE TEMPERATilRE OF ECC llATER) t 3.

REDUCE Tile LIKELIll00D OF REPRESSURIZATION (E.G., OPERATOR PROCEDURES OR CONTROL SYSTEM MODIFICATIONS) fl.

MAINTAlli ilIGil FRACTURE TOUGilNESS OF VESSEL.

(E.G., REMOVE OUTER FUEL TO REDllCE FLUX AT VESSEL) 5.

REGAlfi FRACTURE TOUGilNESS OF VESSEL i

(E.G., IN-PLACE ANNEALI!!G) s

ElilAT SHOULD BE Tile REGULATORY LIMIT?

WHAT SHOULD BE THE DESIGN BASIS TRANSIENTS?

IS RTNDT THE PROPER CRITERION?

1 WHAT Sil00Lb BE Tile LIMIT ON RT

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NDT WHATSHOULDTHEEVALUATIONM0hELFORCALCULATINGRT

?

NDT HOW Sil0ULD UNCERTAINTIES BE TREATED?

SHOULD ONE DIFFERENTIATE BETWEEN CIRCUMFERENTIAL AND LOGITUDINAL WELDS?

RATE OF INCREASE OF RTNDT 1

PLANT CURRENT RT ADDITIONAL EFPY TO REACH RTNDT = 300 F NDT FT. CALHOUN 280 F 2.0 EFPY ROBINSON 2 290 F 1.4 EFPY 0

SAN ONOFRE 1 270 F 2.7 EFPY TURKEY POINT li 280 F 2.2 EFPY MAINE YANKEE 240 F 7.l; EFPY i

CALVERT CLIFFS 1 230 F 3.11 EFPY TMI 1 160 F 10.fi EFPY OCONEE 1 170 F 13.3 EFPY 4

NUMBER OF PLANTS WITH RT AB0VE 200F NDT 4

i RANGE OF RTNDT ( f) l 200-220 220-240 240-260 260-280 280-300 1

i VESSELS HAVING 2

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1 2

LONGITUDINAL WELDS VESSELS HAVING 2

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CIRCUMFERENTIAL WELDS I

+ - -

10 CFR 50 APPENDIX G PARAGRAPil IV

" REACTOR VESSELS FOR WHICH Tile PREDICTED VALUE OF ADJUSTED REFERENCE TEMPERATURE EXCEEDS 200 F SHALL BE DESIGNED TO PERMIT l

A THERMAL ANNEALING TREATMENT TO REC 0VER MATERIAL TOUGilNESS PROPERTIES OF FERRITIC MATERIALS OF THE REACTOR VESSEL BELTING "

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EXAMPLE OF ANNEALING TO MEET RT LIMITS

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EFFECTIVE FULL POWER YEARS e

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EXAMPLE OF ANNEALING TO MEET RTNDT LIMITS i

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STAFF CONCLUSIONS I

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4 STAFF CONCLUSIONS

-- PRESSURIZED THERMAL SH0CK IS A SAFETY CONCERN FOR OLDER PWR VESSELS HAVING HIGH COPPER CONTENT MATERIAL.

-- If1 MEDIATE CORRECTIVE ACTION IS NOT NECESSARY, BUT SUBSTANTIAL WORK IS HEEDED BY THE INDUSTRY DURING COMING YEAR

-- SOME CORRECTIVE ACT10NS WILL LIKELY BE REQUIRED FOR SOME PLANTS WITHIN A YEAR FROM NOW

-- BASES FOR STAFF CONCLUSIONS THAT NO CORRECTIVE ACTIONS ARE REQUIRED NOW:

A)

CHANCES OF A SEVERE OVERC00 LING TRANSIENT IN OLDER PWR PLANT DURING COMING YEAR IS ABOUT 1 IN 100 B)

EVEN IF A TRANSIENT AS SEVERE AS RANCHO SECO WERE TO OCCUR, VESSEL FAILURE WOULD NOT BE PREDIC7ED USING NOMIflAL MATERIAL PROPERTIES C)

ANALYSES INCLUDE A NUMBER OF CONSERVATISMS

l STAFF ACTIONS INDEPENDENT ANALYSES OF IRANSIENTS, FLUENCE AND FRACTURE MECHAfhCS CALCULATIONS REVIEW LICENSEE At1ALYSES 60 DAY REPLIES

- 150 DAY REPLIES

_ GENERIC PEPORTS 6ENERIC RESOLUTION BY STAFF (DRAFT NUREG BY SUMMER 1982)

- POSSIBLE OPERATOR GUIDELINES

- POSSIBLE LIMITS ON RINDT I

i

REFERENCE TEMPERATURE, RTHDT FOR PWR OPERATING PLANTS AT VESSEL INSIDE SURFACE AS OF i4AY 1, 1981 DEFINITION:

RTHDT

=

REFERENCE IEMPERATURE NIL-DUCTILITY IRANSITION RTHDT =

INITIAL RTNDT + aRTHDT INITIAL RTanT IS DETERMINED BY' FOLLOWING ASiiE CODEPROCEbuRES, t iG-2331 l

ART IS THE TEMPERATURE SHIFT IN THE CHARPY iBT TRANSITION CAUSED BY IRRADIATION.

VALUES USED IN THE ATTACHED TABLES ARE FROM dEG. Gu!DE 1.99, REV. 1.

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3 BABC0CK AND WILCOX PLANTS Vessel Effective Fluence Per EFPY Percent Copper Reference i merature, Plant Fabricator Full Power Cir.

Lo 19 Cir.

Long.

Rinor De ahr.

Years Welds Welds Welds Welds Plate Cir. Weld long. Wrids 18 2

18 2

x10 n/cm x.0 n/cm Oconee 1 B&W 4.89 0.54 0.46 0.26 0.31 150 170 Three Mile Is. 1 B&W 3.4S 0.60 0.60 0.35 0.31 160 160 Rancho Seco B&W 3.25 0.66 0.58 0.31 0.31 160 150 Arkansas 1 B&W 3.Bs 0.61 0.45 0.31 0.31 170 150 Crystal River 3 B&W 2.18 0.50 0.55 0.35 0.31 150 130 Oconee 2 B&W 4.26 0.61 Forgings 0.35 forgings 200 Forgings Oconee 3 B&W 4.3 0.61 Forgings 0.24 Forgings 140 Forgings Davis Besse B&W l.26 0.66 Forgings 0.24 Forgings 60 forgings

6 COMBUSTION ENGINEERING PLANTS Reference i c.ncra tu re,

Vessel Ef fective Fluence Per EFPY Percent Cqpper RTNOT De

'ahr.

Plant Fabricator Full Power Cir.

L)ng.

h'i r.

Long.

Plate Cir. Weld iong. Welds Years Welds Walds Welds Welds I0 2

I0 x10 n/cm x10 n/cm Fart Calhoun CE 4.76 1.12 1.72 0.35 0 15 280 280 Maine Yankee CE E.50 0.85 0.85 0.36 0.36 240 240 Calvert Cliffs 1 CE 4.10 1.47 1.47 0.30 0.30 230 230 Calvert Cliffs 2 CE

3. 0'3 1.47 1.47 0.23 0.30 150 200 Palisades CE 3.92 1.16 1.16 0.25 0.25 190 190 Millstone 2 CE 3.37 0.56 0.56 0.37 0.37 160 160 St. Lucie CE 3.31 0.63 0.63 0.31 0.30 140 140 Arkansas 2 CE 0.69 l

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a Page 1 of 2 j

WESTINGII0llSE PLANTS i

Reference 1

rcrature, Vessel Effective fluence Per EFPY Percent Copper RTHDT Ocp. I,ihr.

Plant Fabricator Full Power cir.

Elihg.

Cir.

Long.

Plate Cir. Welds l ong. Welds Years Welds Welds Welds Welds I0 2

I0 2

x10 n/cm 10 n/cm Robinson 2 CE 6.80 1.72 1.59 0.34 0.3'4 290 290 San Onofre CE 8.62 1.74 1.74

' O.19 0.19 270 270 fladdam Neck CE 10.52, 1.31 1.09 0.22 0.22 230 220 Point Beach 1 B&W 7.69, 1.24 0.91 0.24 0.24 220 210 Surry 2 B&W/ RIM 4.34 1,56 0.34 0.19 0.31 140 110 Zion 2 B&W 4.16 0.63 0.20 0.26 0.35 120 100 Zion 1 B&W 4.32 0.63 0.20 0.35 0.31 170 90 Farley TE 1.86 1.69 0.38 0.24 0.27 120 70 Surry 1 B&W 4.51 1.56 0.34 0.25 0.18 190 60 Beaver Valley CE 1.33 1.69 0.25 0.3T 0.36 160 60 Cock 1 CE 4.15 0.63 0.34 0.40 0.13 170 50 Cook 2 CB&I 2.00 Sequoyah 1 RDM 0.20 Yankee Rowe B&W 14.14 0.78 Plate 0.20 Plate 200 No weld data Indian Point 2 CE 3.97 0.50 Plate 0.25 Plate 140 No weld data a

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WESTINGil00SE PLANTS 4

Reference

'peratin e, Vessel

ffective Fluence Per EfPY Percent Copper RTNDT Dei Fa hr.

Plant Fabrica tor roll Fower cir.

long.

Cir.

Long.

Plate Cir. Weld fing. LbbIs Years Welds Welds Welds Welds 18 2

I0 2

x10 n/cm x10 n/cm Indian Point 3 CE 2.6/

0.56 Plate 0.24 Plate 120 Plate i controlling Salem 1 CE 1.76 1.16 Plate 0.24 Plate 90 Plate i controiling Trojan CB&I 2.57 0.69 Plate 0.15 Plate 60 Plate :. <.ontroll itig Turkey Point 3 B&W

5. 6,7 1.97 0.31 290 forgings Turkey Point 4 B&W 5.16 1.97 0.30 280 forgings Point Beach 2 B&W/CE 6.96 1.24 0.25 240 Forgings Ginna B&W 7.66 1.16 0.25 220 Forgings Kewaunee CE 5.32 1.34 0.20 150
forging, Prairie Is. 2 SFAC 5.11 1.34 0.19 140 forginns Prairie Is. 1 SFAC 5.36 1.34 0.14 100 forgings North Anna 1 RDM 1.90 1.78 0.14 110 forgings North Anna 2 RDM 0.35 1.78 0.13 90 forgings

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TRANSMITTAL '10:

Document Control Desk, c

016 Phillips M

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ADVANCED COPY TO:

O The Public Document Pr oom DATE:

September 16, 1981 a

w Attached are the PDR copies of a Commission meeting h

transcript /s/ and related meeting document /s/.

They p

are being forwarded for entry on the Daily Accession P

List and placement in the Public Document Room.

No P

other distributien is requested or required.

Existing DCS identification numbers are listed on the individual

~

documents wherever possible.

1.

Transcript of:

Briefing on Pressurized Thermal' Shock, September 15, 1981.

(1 copy) a.

SECY-81-286A, Policy Issue Paper dated Sep.

8.

81, Subj; Pressurized Thermal Shock of Pressure Vessels.

(1 cony) b.

Copy of vugraphs presented at above meeting.

(1 copy).

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