ML20114A829

Forwards Revised Ref Temps for PTS Calculated Per 10CFR50.61, Fracture Toughness Requirements for Protection Against PTS Events, Utilizing Methodology Delineated in Rev 2 to Reg Guide 1.99

ML20114A829
Person / Time
Site:	Seabrook
Issue date:	08/17/1992
From:	Feigenbaum T NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-REGGD-01.099, RTR-REGGD-1.099 NYN-92112, NUDOCS 9208240004
Download: ML20114A829 (5)

Text

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r eab k NH 03074 a Telephone (603)474 9521 f

jh h FLcsimile (603)474 2987

. Energy Service Corporation Ted C Felgenbaum Senior Vice President and i Chief Nuclear Officer NYN-92112 ,

i August 17, 1992 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk

References:

(a) Facility Operating License No. NPF-86, Docket No. 50-443 (b) NHY Letter, NYN-88090 dated July 8, 1988,

• Projected Reference Temperature Values for Pressurized Thermal Shock Eve n t s," U. S.

Thomas to USNRC (c) North Atlantic Letter, NYN-92111 dated August 17, 1992 " License Amendment Request 92-06: Revised RCS Pressure / Temperature Limits",

T. C. Feigenbaum to USNRC

Subject:

Revised Reference Temperature Values for Pressurized Thermal Shock Events Gentlemen:

North Atlantic Energy Service Corporation (North Atlantic) prov' les revised Reference Temperatures for Pressurized Thermal Shock (RTpts) for Seabrook Station in Enclosure 1.

The revised values were calculated in accordance with 10CFR50,61 " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Even ts" utilizing the methodology delineated in Revision 2 to Regulatory Guide 1.99, " Radiation Einbrittlement of Reactor Vessel Materials" The revised RTns values supersede the values that were submitted on July 8,1988 [ Reference (b)). A cmy of the July 8,1988 letter is provided in Enclosure 2.

The revised RTers values were developed by Yankee Atomic Electric Company Nuclear Services Division (YNSD) for the Seabrook Station Unit I reactor vessel. For all reactor vessel locations, the value for RTers at the end of licensed life (32 EFPY) is significantly less than the screening value, in ~ a separate transmittal dated August 17, 1992 [ Reference (b)) North Atlantic submitted License Amendment Request 92-06 which proposes to revise the Seabrook Station Technical Specification Pressure / Temperature Limits. The enclosed RTpy3 values are being submitted concurrent with the submittal of License Amendment Request 92-06 as required by 10CFR50.6L i

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b a member of the Northeast Utilities system 0 l 9208240004 920817

PDR ADOCK 05000443 \\

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' United States Nuclear Regulatory Commission August 17, 1992

- Attention:

Document Control- Desk Page two

• . Should you have any questions or require further assistance, please contact Mr. James M. Peschel, Regulatory Compliance Manager, at'(603) 474 9521 extension 3772.

Very truly yours,

/ '

Ted C. Feigenba t TCF:M DO/ss/ tad -

cc: Mr. Thomas T. Martin Regional Administ'rator U. .S. Nuclear Regulatory Commissioc Region I 475 Allendale _ Road

- King _of Prussia, PA- 19406 Mr. Gordon E. Edison, Sr. Project Manager Project Directorate'l 3 .

- .. Division of- Reactor Projects'.

U.S; Nuclear Regulatory Commis* ion

--Washington, DC- 20555 Mr.! Noel Dudley -

NRC Senior.. Resident Inspector P.O. Box 1149 Seabrook, NH 03874

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North Atlantic En'ergy Service Corporation August 17, 1992

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- ENCLOSURE 'l TO NYN-92112 t-L f

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RTn3 UALUES -'SEABROOK UNIT NO.-l1_ REACTOR UESSEL'

.2 EFPY: .Cu Ni I*:+ lM t+ ART ns. =

RTns SCREENING

_ . COMPONENT. ' CODE N0'. FLUENCE- .(Wtg.Z) '~

g (Wtg .' Z ) ~(*F)= (*F) (*F) (*F)- '. VALUE/ *F :- -

2 (n/cm ) ,

- Intermediate Shell R1806-1 . 3.1 j x '101 ' ' . 0. 04 ' O.64 40- +- 34 + 34 = 108. ~ 2 7 0. '

Intermediate

- Shell R1806-2? 3;l x 10.' 1

~0. 0 5' . 'O.65 0 '+ . 34 + 41 '= 75 270 4

Intermediate _ .

Shell' R1806-3' 3.1 x:10 ' 1

'0.07 0.65 10 + 34 .+ 58 = 102 270' 4

Lower Shell R1808-1 3.1 x 10 ' 1 O.05 0.58 40 '+ 34 + 41 = 115 270

. Lower Shell RIS08-2' 3.1 x'10 19 0.05 0.57 10 + 34 + 41 = S5 270 Lower Shell R1808-3 3.1 x'10 ' 1 O.06' 0.57 40 +. 34 + 48 = 122 270 Inter to Lower.

Shell Girth Weld Seam G1. 72' '3.1 x 10 ' 1

'O.07 0.02 -50.+ 56 + '45 = 51 300 Inter and Lower Shell Long Weld .7 Seam G1.72 3.1 x 10 '"-1 0.07 0.02 -50 + 56 + 45 = 31 270

• All of the initial reference temperatures that are shown are measured values.

• • Although only a few of these six longitudinal welds are located near the peak flux regions around the core, the. peak fluence was used for all of the longitudinal-welds as a conservatism.

DEFINITIONS I' - Initial Reference Temperature of the unirradiated material as defined.in ASr. Code Section'III, PP NB-2331.

M - Margin to cover uncertainties in material properties as defined in 10CFR50.61(b)(11).

RTns - . I + M + ARTns s __ . .

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I ., . North Atlantic Energy; Service Corporation August 17, 1992 1) o, < -

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George S. Thomas -

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! NYN- 88090 i Mblic Service of New Hampshire- July 8, 1988

' New $ampshire Yankee DMsion - .

United' States Nuclear Regulatory Commission Washington, D.C. 20555

-Attention: Document Control Desk

Reference:

Facility Operating License No. NPF-56, Docket No. 50-443

Subject:

' Projected Reference Temperature Values For Pressurized Thermal Shock Events Gentlemen This is provided(in ges,ponse to:a request-by.the NRC.Staffifor dnfo'rdstionp' ettaining sto the ref erence -temperatures"(RT)'for pressurized $

tthermal-shocks (PTS)*cvents. Enclosure 1 provides data developed for New Hampshire Yankee (NHY) by Vestinghoust Electric Corporation for the Seabrook Station Unit I reactor vessel. The Westinghouse information is based on the

- methods and generic assessment as outlined in 10CFR50761'(b)', and is provided

'in Enclosure-2. . Westinghouse has provided the same calculations for other similarly-designed Pressurized Water Reactors.

Should you have any questions or require further' assistance, please contact'Mr. Timothy G. Pucko at (603) 474-9574 extension 4428.

Very truly yours, d

Geor . Thomas

'Esclosure ce s. Mr.' Victor Nerses, Project Manager Project Directorate I-3

-. Division of Reactor. Projects United States Nuclear Regulatory Comission Washington,-.DC- 20555 Mr. Villiam T. Russbil Regional Administrator

~ United States Nuclear Regulatory Comission Region I 425 Allendale Road f . ,,,eg . ' King of Prussia, PA 19406 f

'Mi[7-s Mr.-Antone C. Cerne NRC Senior Realdent Inspector ,

I

'Seabrook Station

,Seabrook, NH 03874 O h94p.O. Box 300 . Seabrook, NH 03874 . Telephone (603) 474-9574

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ENCLOSURE 1 TO NYN . 88090 -

t RTpyn VALUES - SEAEROCK UNIT NO. 1 REACTOR VESSEL ,

32 EFPY Cu N1 I* + M + ARTNDT

• EIFTS SCFEENING COMPONENT CODE FO. FLUENCE (n/cm2) (Wtg.2) (Weg.I) (*F) (*F) (*F) (*F) VALUE/*F i

Intermediate Shell R1806-1 3.1 x 1019 0.04 0.64 40 + 48 + 24 - 112 270

~ntermediate Shell R1806-2 3.1 x 1019 0.05 0.65 0 + 48 + 34 - 82 270 Intermediate Shell R1806-3 '3.1 x 1019 0.07 0.65 10 + 48 + 53 - '11 270

~

Lower Shell R1808-1 3.1 x 1019 C.05 0.58 40 + 43 + 32 - 120 270 Lower Shell R1808-2 3.1 x 1019 0.05 0.57 10 + 43 + 32 -

90 270 Lower Shell R1803-3 3.1 x 1019 0.06 0.57 40 + 48 + 41 - 129 270

~

Inter to Lower Shell G1.72 3.1 x 1019 0.07 0.02 -50 + 48 + 32 - 30 300 ,

Girth Weld Seam .

Inter and Lower Shell C1.72 3.1 x 1019 ** 0.07 0.02 -50 + 48 + 32 -

30 270 Long Veld Scam

• All of the initial refere: e temperatures that are shown are measured valves.

• • Although only a few of these six longitudinal welds are located near the peak flux regions around the core, the peak fluence was used for all of the longitudinal welds as a conservatism.

DEFINITIONS:

1 - Initial Reference Temperature of the unirradiated material as defined in ASME Code S : tion III, PP NB-2331.

M - Margin to cover uncertainties in material properties as defined in 10CFR30.61(b)(ii).

RTFTS - I+M+RTNDT- .

I

INCLOSURE T 70 HYN- 88090 THE CALQULATION OF ET ,

e pts

!'nb}@:.

In the PTS Rule, the NRC Staff has selected a conservative and uniform method for determining plant-specific valves of RTPTS at a given time. The prescribed equations in the PTS Rule for calculating RTPTS are actually one of several ways to calculate RTHDT. For the purpose of comparison with the Screening Criterien the value of KTp73 for the reactor vessel must be calculated for each veld and plate, or forgoing in the beltline region as given below. F>r each material, RTp73 is the lover of the results given by Equatiens 1 a*.1 2.

Equation 2:

0.270 RTPTS " I + N *s [-10 + 470(Cu) + 350(Cu)(Ni)) f A EI NDT Equation 2:

0 RT PTS = I + M +%283 f 194 <

A RT NDT vhere, I means the initial reference trancition temperature of the unirradicted

%g f

o material measured as defined in the ASMI Code, PP NB-2331. If a measured hF value is not available, tha following generic mean values must be used:

0 F for velds made with Linde 80 flux, and -56 0F for velds made with Linde 0091, 1092 and 124 and ARCOS E-5 veld fluxes.

H means the margin to be added to cover uncertainties in the values of initial RTNDT, copper and nickel content, fluence, and calculation procedures. In Equation 1, M-48 F if a measured value of I va; used, and M-59 F if the generic mean value of I was used. In Equation 2, M-0 F if 0

a measured value of I was used, and M-34 F if the generic mean value of I was used.

Cu and Ni means the best estimate weight percent of copper and nickel in the traterial, f means the maximum neutron fluence, in units of 1019n/cm2 (E greater than or equal to 1 MeV). at the clad-base-metal interface on the inside surface of the vessel at the location where the material in question receivts the highest fluence for the period of service in question.

Note that since the chemistry valurs given in Equations 1 anr' 2 are best estimate mean values, and the margin, M, causes RTPTS valuer to be upper bound predictions, the mean material chemistry values are to be e d, when available, so as not to compound conservatism.

M W.

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