ML17310B379

Informs That Util 920727 Responses to GL-92-01,rev 1 Re Reactor Vessel Structural Integrity Has Been Provided. Verification of Info Entered Into Data Base Requested

ML17310B379
Person / Time
Site:	Palo Verde
Issue date:	06/20/1994
From:	Brian Holian Office of Nuclear Reactor Regulation
To:	Stewart W ALABAMA PUBLIC SERVICE CO.
References
GL-92-01, GL-92-1, TAC-M83492, TAC-M83493, TAC-M83494, NUDOCS 9406270057
Download: ML17310B379 (22)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 20, 1994'ocket Nos.

STN 50-528, STN 50-529, and STN 50-530 Mr. William L. Stewart Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999

Phoenix, Arizona 85072-3999

SUBJECT:

GENERIC LETTER (GL) 92-01, REVISION 1, "REACTOR VESSEL STRUCTURAL INTEGRITY" PALO VERDE NUCLEAR GENERATING STATION, UNITS 1, 2, AND 3 (TAC NOS.

M83492, M83493, M83494)

By letter dated June 27, 1992, Arizona Public Service Company (APS) responded to GL 92-01, Revision 1.

The NRC staff has completed its review of your response.

Based on its review, the staff has determined that APS has provided the information requested in GL 92-01.

The GL is part of the staff's program to evaluate reactor vessel integrity for pressurized-water reactors (PWRs) and boiling-water reactors (BWRs).

The information provided in response to GL 92-01, including previously docketed information, is being used to confirm that licensees satisfy the requirements and commitments necessary to ensure reactor vessel integrity for their facilities.

A substantial amount of information was provided in response to GL 92-01, Revision 1.

These data have been entered into a computerized data base designated Reactor Vessel Integrity Database (RVID).

The RVID contains the following tables:

a pressurized thermal shock (PTS) tabl.e for PWRs, a

pressure-temperature limit table for BWRs, and an upper-shelf energy (USE) table for PWRs and BWRs.

Enclosure 1 provides the PTS table, Enclosure 2

provides the USE table for your facilities, and Enclosure 3 provides a key for the nomenclature used in the tables.

The tables include the data necessary to perform USE and RT evaluations.

These data were taken from your response to GL 92-01 and previously docketed information.

References to the specific source of the data are given in the tables.

We request that you verify the information you have provided for your facilities has been accurately entered in the summary data file.

No response is necessary unless an inconsistency is identified. If no comments are received within 30 days of the date of this letter, the staff will consider your actions related to GL 92-01, Revision 1, to be complete and will use the information in the tables for future NRC assessments of your reactor pressure vessel.

9406270057 940620 PDR ADOCK 05000528' PDR

Mr. William L. Stewart The information requested by this letter is within the scope of the overall burden estimated in GL 92-01, Revision 1, "Reactor Vessel Structural Integrity, 10 CFR 50.54(f)."

The estimated average number of burden hours is 200 person-hours for each addressee's response.

This estimate pertains only to the identified response-related matters and does not include the time required to implement actions required by the regulations.

This action is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.

Sincerely, ORIGINAL SIGNED BY:

Brian E.

Hol i an, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Enclosures:

1.

Pressurized Thermal Shock Table (3) 2.

Upper-Shelf Energy Table (3) 3.

Nomenclature Key cc w/enclosures:

See next page DISTRIBUTION:

~Docket F,il.e~

PDIV-2 Reading EAdensam BHolian DMcDonald ACRS (10)

DFoster-Curseen NRC

& Local PDRs JRoe TQuay LTran'GC

KPerkins, RIV/WCFO OFFICE NAME DATE DRPW/LA DFoster-Curseen

/

94 PDIV-PM BHolian: k 6

K 94 PDIV-D TQuay Cu /go/94 OFFICIAL RECORD COPY DOCUMENT NAME:

PVGL9201

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Hr. William L. Stewart The information requested by. this letter is within the scope of the overall burden estimated in GL 92-01, Revision 1, "Reactor Vessel Structural Integrity, 10 CFR 50.54(f)."

The estimated average number of burden hours is 200 person-hours for each addressee's response.

This estimate pertains only to the identified response-related matters and does not include the time required to implement actions required by the regulations.

This action is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.

Sincerely, ORIGINAL SIGNED BY:

Brian E.

Hol i an, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Enclosures:

1.

Pressurized Thermal Shock Table (3) 2.

Upper-Shelf Energy Table (3) 3.

Nomenclature Key cc w/enclosures:

See next page DISTRIBUTION:

Docket File PDIV-2 Reading EAdensam BHolian DMcDonald ACRS (10)

DFoster-Curseen NRC

& Local PDRs JRoe TQuay LTran OGC

KPerkins, RIV/WCFO OFFICE DRPW LA PDIV-~PH PDIV-D NAME DATE DFoster-Curseen

/

94 BHolian: k 6

JC 94 TQuay go /94 OFFICIAL RECORD COPY DOCUMENT NAME:

PVGL9201

'h I

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Hr. William L. Stewart The information requested by this letter is within the scope of the overall burden estimated in GL 92-01, Revision 1, "Reactor Vessel Structural Integrity, 10 CFR 50.54(f)."

The estimated average number of burden hours is 200 person-hours for each addressee's response.

This estimate pertains only to the identified response-related matters and does not include, the time required to implement actions required by the regulations.

This action is covered by the Office of Hanagement and Budget Clearance Number 3150-0011, which expires June 30, 1994.

I Sincerely, I

Brian E. Holian, Project Hanager Project Directorate IV-2 Division of Reactor Projects..III/IV Office of Nuclear Reactor Regulation

Enclosures:

1.

Pressurized Thermal Shock Table (3) 2.

Upper-Shelf Energy Table (3) 3.

Nomenclature Key cc w/enclosures:

See next page

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Hr. William L. Stewart Arizona Public Service Company Palo Verde CC:

Hr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street

Phoenix, Arizona 85007 T.

E. Oubre, Esq.

Southern California Edison Company P.

O.

Box 800

Rosemead, California 91770 Senior Resident Inspector Palo Verde Nuclear Generating Station 5951 S. Wintersburg Road

Tonopah, Arizona 85354-7537 Regional Administrator, Region IV U. S. Nuclear Regulatory Commission Harris Tower & Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Hr. Charles B. Brinkman, Hanager Washington Nuclear Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Haryland 20852 Hr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street

Phoenix, Arizona 85040 Jack R.

Newman, Esq.

Newman

& Holtzinger, P.C.

1615 L Street, N.W., Suite-1000 Washington, D.C.

20036 Hr. Curtis Koskins Executive Vice President and Chief Operating Officer Palo Verde Services 2025 N. 3rd Street, Suite 220 Phoenix, Arizona 85004 Roy, P.. Lessey..Jr.,

Esq.

Akin, Gump, Strauss, Hauer and Feld El Paso Electric Company 1333 New Hampshire Avenue, Suite 400 Washington, DC.

20036 Hs. Angela K.--Krainik, Hanager Nuclear Licensing Arizona Public Service Company P. 0.

Box 52034

Phoenix, Arizona 85072-2034

Chairman, Haricopa County Board of Supervisors

'11 South, Third Avenue

.Phoenix, Arizona 85003

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ENCLOSURE 1

Summary File for Pressurized Thermal Shock Plant Kame 8eltlinc Ident.

Neat No.

Ident.

ID Naut.

Fluence at EOL Hethod of Determin.

IRT Chemistry Factor Hethod of XCu oetermin.

CF PaL0 verde 1

Lower shell H.4311.1 3.29E19

-10'F Plan't Specific 26 Table 0.04 0.65 EOL:

12/31/

2024 Lower shell H.4311-2 3.29E19

.40'F

Plant, 20 Speci fic Table 0.03 0.62 Refererees Lo~er shell H-4311.3 Int. shell H-6701-1 tnt. sheLL H.6701-2 lnt. shell N-6701.3 lnt. shell axial welds 101-124A/C Lower shell ax'Iel welch 10'I 142A/C Circ. weld 101-171 NIL 8-4 wire HIL 8.4 wire HIL 8 4 wire 3.29E19 3.29E19 3.29819 3.29E19 3.29E19 3.29E19 3.29819 20'F 30oF 400F 40'F 50'F,

.80'F

-70'F Plant Specific Plant S

If ic

PLant, S

ific PLant S

Ific Plant.

Speci fic Plant Speci fic Plant. 'ific 20 37 37..

35.45, 27.8 34.05 Table Table Table Table Table Table Table 0.03 O.O7 0.06 0.06 0.05 0.04 0.04 0.64 0.66 0.61 0.61 0.03 0.05 0.09 Fluence and IRT data are fran January 31, 1989, Letter fran D. S. Karner (APS) to USNRC Oocunent Control Desk, subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3, Generic Letter 88-11,.Radiation Embrittlement of Reactor Vessel Haterials Meld chemicaL cceposition values are averages fran data in the first reference and data fran FSAR.

NCLOSURE 2 Summary File for Upper Shelf Energy Plant Name geltline ident.

Heat No.

Hateriel Type 1/4T USE at EOL 1/4T Neutron Fluence at EOL Unirrad.

USE Hethod of Oetersin.

Unirrad.

USE Palo Verde 1

EOL:

12/31/

2024 Lover sheLL H.4311 1

LoMer shell H-4311.2 Lover sheLL H-4311-3 Int. shell H-6701

'1 tnt. sheLL H.6701-2 lnt. sheLL H-6701-3 A 533$ -1

104, A 533$

1 A 533$.1 111 A 533$ -1 65 A 533$ -1 75.

A 533$ -1 79 1.91E19

1.91E19 1.91E19 1.681E19 1.681E19 1.681E19 127 142 Direct Direct Direct Direct Direct Direct Refereeeee.

lnt. shell exiaL welch 101-124A/C Lover shell axiaL molds 101.142A/C Circ. veld 101-171 HLL $.4 Mire HLL $

4 Mire

)llL 8-4 Mire Linda 0091 SAM Linda 0091 SAM Linda 124 SAM 59 71 1.681 E19 1.91E19 1.681 E19 7Ss 140 NRC Generic Direct Direct Fluence and IRT~ data are frcxs January 31, 1989, Letter fras D. 8. Karner (APS) to USNRC Docunent Control Desk, subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3, Generic Letter 88.11, Radiation Eshrittlenent of Reactor Vessel Hateriala information on plate end weld material types ia frees FSAR; plate WSE data are fras Table 5.2-5A of FSAR, and ueld UUSE values are frcxs Charpy curves of FSAR.

FSAR does not have Charpy curves for zelda 'l01-124 A/C that uaa fabricated by using HtL 8-4 eire and Linda 0091 flux.

Aa a result, NRC generic value uas used (see Footnote 5).

Generic value for welds fabricated by Combustion Engineering using Linde

1092, 0091, 124 and Arcos B-5 fluxes (Ref. Letter from S.

Bloom of USNRC to T.L. Patterson of Omaha Public Power District, dated December 3, 1993).

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Summary File for Pressurized Thermal Shock ENCLOSURE 1

Plant Name Beltline Heat No.

Ident.

Ident.

10 Haut.

Fluence at EDL Hethod of Determin.

IRT Chemiatry Factor Hethod of XCu Determin.

CF PeLQ Verde 2 LoMer shell F-773-1 3.29819 10'F Plant Specific 20 Table 0.03 0.67 EOL:.

12/9/2025 Lover sheLL F-773-2 3.29E19 O'

Plant, 2S Speci fic Table 0.04 0.64 Lover sheLL F-773.3 3.29E19

-60'F Plant Speci fic 31 Table 0.05 0.66 Int. sheLL F 765 4 3.29E19

-20'F PLant 5

Ific 20 Table 0.03 0.67 Int. sheLL F.765-5 3.29E19 10'F Plant 20 S

ific Table 0.03 0.65

~RRfe rene R Int. sheLL F 765 6 Int. shelL Ix)eL zelda 101.124A/C Lover shell aciel Holds 101 142A/C Circ. Meld 101.171 HIL 8 4 Mire HIL $ 4 Mire HILB4 Mire 3.29E19 3.29E19 3.29E19 3.29E19 10'F

-60'F

.80'F

.30'F Plant S

if ic PLant Speci fic Plant Speci fic Plant S

if ic 26 35.2 37.75 Table Table Tabt ~

Table 0.04 OR 06 0.08 0.03 0.67 O.OS 0.05 0.10 Fluence and IRT date are from January 3'I, 1989, letter froa D. B. Karner (APS) to USNRC Dona>>nt Control Desk, subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3, Generic Letter 88-11, Radiation Eehrittlement of Reactor Vessel Haterials Meld chemical composition values are averages free data in the first reference end data from FSAR.

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ENCLOSURE 2 Summary File for Upper Shelf Energy Plant Name Belt line ident.

Neat No.

Haterial Type 1/4T USE at EOL 1/4T Neutron Fluence at EOL Unirred.

USE Hethod of Oeterain.

Unirrad.

USE P@LO Verde 2 EDL:

12/9/202 5

References LoMer shell

. F-773-1 Lover shell F.773 2 Lover shell F-773-3 int. sheLL F.765-4 int. shelL F.765-5 int. shell F-765.6 1nt. shell ax'ial voids 101.124A/C Loaer shell ax'ieL zelda 101.142A/C Circ. 'Weld 101-171 HLL B 4 ltire H1L 8 4 ltire H1L B.4 ltire A 533B-1 82 A 533B-1 99 A 5338 1

100 A 533S-1 90 A 5338-1 95 A 5338.1 99 Linda 124 SAM Linda 124 76 SAlt Linda 124 SAM 1.91E19 1.91E19 1.91E19 1.681E19 1.681 E19 1.681E19 1.681 E19 1.91E19 1.681E19 105 127 121 100 Direct Direct Direct Direct Direct Direct Direct Direct Direct Fluence and 1RT data are fras January 31, 1989, letter fraa D. B. Karner (APS) to USNRC Oocunent Control Desk, subject:

Palo Verde Nuclear Generating Station

<PVNGS) Units 1, 2, and 3, Generic Letter 88-11, Radiation Eahrittlement of Reactor Vessel Hateriala information on plate and ueld materi ~ L types is fraa FSAR; plate WSE data are from Table 5.2-5A of FSAR, and Hald WSE values are fraa Charpy curves of FSAR.

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Summary File for Pressurized Thermal Shock ENCLOSURE 1

Plant Name Palo Verde 3 EOL:

3/25/2027

References:

Beltline Ident.

Lover shell F-6411-1 Lover shell F.6411-2 Lover shell F.6411-3 Int. sheLL F 6407 4 Int. shell F-6407.5 Int. shell F-6407-6 Int. shell axial fields 101.124A/C Louer shell axial uelds 101-142A/C Circ. Meld 101-171 Neat No~

Ident.

HIL 8-4 Mire HIL 84 Mire HIL 84 Mire IO Naut.

Fluence at EOL 3.29E19 3.29E19 3.29E19 3.29E19 3.29E19 3.29819 3.29E19 3.29E19 3.29E19

.40'F O'

.60'F

.30'F

.20'F 20'F

.50'F

.50'F

-70'F Hethod of Oetermin.

IRT Plant Speci fIc Plant Speci fic PLant Specif ic Plant S

ific Plant S

ific Plant S

If ic Plant Specific Plant Speci fIc PLant S

Ific Chemistry Factor 26 26 26 26 31 26 22.75 26.05 Hethod of Oetermin.

CF Table Table Table Table Tabl ~

Table Table Table Table 0.04 0 04 0.04 0.04 0.05

'.04 0.03 0.04 0.04 0.64 0.65 0.66 0.62 0.61 0.61.

0.07.

0.06 0.14 Fluence and IRT data are fran January 31, 1989, Letter fran O. B. Karner (APS) to USNRC Doasnent Control Desk, subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3, Generic Letter M-11, Radiation Embrittlement of Reactor VesseL Haterials Meld chemical canposition values are averages fran data In the first reference and data fraa FSAR.

ENCLOSURE 2 Summary File for Upper Shelf Energy Plant Name Belt tine Ident.

Heat No.'ateriel Typ 1/4T USE at EOL 1/4T Neutron Fluence at EOL Unirrad.

USE Kethod of Determin.

Unirrad.

USE Palo Verde 3 EOL:

3/25/202 7

Loaer shell F-6411.1 Lover shell F.6411-2 LoMer shell F-6411-3 Int. shell F-6407 4 tnt. shell F.6407.5 Int. shell F-6407.6 Int. shell axial weids 101-124A/C Lover shell axial voids 101-142A/C HIL 84 Mire HIL 8.4 Mire A 5338.1 122 A 5338.1 87 A 5338-1 83 A 5338.1 101 A 5338-1 90 A 5338-1 105 Linda 124 SAM Linda 124 SAM 1.91E19 1.91E19 1.91E19 1.681 E19 1.681E19 1.681E19 1.681 E19 1.91E19 156 107 114 133 100 100 Direct Direct Direct Direct Direct Direct Direct Direct Ccfcrccccc Circ. veld 101-171 HIL 8.4 llire Linda 124 SAN 71 1.681E19 Direct Fluence and IRT~ data are fras January 31, 1989, letter fras D. B. Karner (APS) to USNRC Doc+sent Control Desk, subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3, Generic Letter M-11, Radiation Eahrittlement of Reactor Vessel Haterials Information on plate and ueid material types ia fras FSAR; plate WSE data are fras Table 5.2-5A of FSAR, and Held WSE values are from Charpy curves of FSAR.

ENCLOSURE 3 PRESSURIZED THERMAL SHOCK TABLES AND USE TABLES FOR ALL PWR PLANTS N

MENCLATURE Pressurized Thermal Shock Table Column Column Column Column Column Column 1':

3

~

4

~

5

~

6:

f Plant name and date of expiration of license.

Beltline material location identification.

Beltline material heat number; for some welds that a single-wire or tandem-wire process has been reported, (S) indicates single'ire was used in the SAW process, (T) indicates tandem wire was used in the SAW process.

End-of-life (EOL) neutron fluence at vessel inner wall; cited directly from inner diameter (ID) value or calculated by using Regulatory Guide (RG) 1.99, Revision 2; neutron fluence attenuation methodology from the quarter thickness (T/4) value reported in the latest submittal (GL 92-01, PTS, or P/T limits submittals).

Unirradiated reference temperature.

Method of determining unirradiated reference temperature (IRT).

tttt-St This indicates that the IRT was determined from tests on material removed from the same heat of the beltline material.

Column Column 7

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8:

MTEB 5-2 This indicates that the unirradiated reference temperature was determined from following MTEB 5-.2 guidelines for cases where the IRT was not determined using American Society of Mechanical Engineers Boiler and Pressure Vessel

Code,Section III, NB-2331, methodology.

Generic This indicates that the unirradiated reference temperature was determined from the mean value of tests on material of similar types.

Chemistry factor for irradiated reference temperature evaluation.

Method of determining chemistry factor.

Table This indicates that the chemistry factor was determined from the chemistry factor tables in RG 1.99, Revision 2.

Calculated This indicates that the chemistry factor was determined from surveillance data via procedures described in RG 1.99, Revision 2.

~ 0 0

t t

1

Column 9

~

Copper content; cited directly from licensee value except when more than. one value was reported.

(Staff used the average value in the latter case.)

No Data This indicates that no copper data has been reported and the default value in RG 1.99, Revision 2, will be used by the staff.

Column 10: Nickel content; cited directly from licensee value except when more than one value was reported.

(Staff used the average value in the latter case.)

No Data This indicates that no nickel data has been reported and the default value in RG 1.99, Revision 2, will be used by the staff.

Upper Shelf Energy Table Column Column Column Column Column Column 1

~

2:

3

~

4

~

5

~

6:

Plant name and date of expiration of license.

Beltline material location identification.

Beltline material heat number; for some welds that a single-wire or tandem-wire process has been reported, (S) indicates single wire was used in the SAW process.,

(T) indicates tandem wire was used in the SAW process.

Haterial type; plate types include A 533B-l, A 302B, A 302B Hod.,

and forging A 508-2; weld types include SAW welds using Linde 80,

0091, 124,

1092, ARCOS-B5 flux, Rotterdam welds using Graw Lo, SHIT 89, LW 320, and SAF 89 flux, and SHAW welds using no flux.

EOL upper-shelf energy (USE) at T/4; calculated by using the EOL fluence and either the cooper value or the surveillance data.

(Both methods are described in RG 1.99, Revision 2.)

EMA This indicates,-that the USE issue may be covered by the approved equivalent margins analysis in a topical report.

EOL neutron fluence at 'T/4 from 'vessel inner wall; cited directly from T/4 value or calculated by using RG 1.99, Revision 2, neutron fluence attenuation methodology from the ID value reported in the latest submittal (GL 92-01, PTS, or P/T limits submittals).

j

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l3 Column 7:

Unirr adiated USE.

EMA This indicates that the USE issue may be covered by the approved equivalent margins analysis in' topical report.

Column 8:

Method of determining unirradiated USE.

Direct For plates, this indicates that the unirradiated USE was from a transverse specimen.

For welds, this indicates that the unirradiated USE was from test date.

65'X t"

This indicates that the unirradiated,USE was 65K 'of the USE from a longitudinal specimen.

Generic This indicates that the unirradiated USE was reported by the licensee from other plants with similar materials to the beltline material.

This indicates that the unirradiated USE was derived by the staff from other plants with similar materials to the beltline material.

10 30 40 or 50 'F This indicates that the unirradiated USE was derived from Charpy test conducted at 10, 30, 40, or 50 'F.

Surv.

Weld This indicates that the unirradiated USE was from the surveillance weld having the same weld wire heat number.

E uiv. to Surv.

Weld This indicates that the unirradiated USE was from the surveillance weld having different weld wire heat number.

Sister Plant This indicates that the unirradiated USE was derived by using the reported value from other plants with the same weld wire heat number.

Blank Indicates that there is insufficient data to determine the unirradiated USE.

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