ML18096B497

St. Lucie, Unit 1 - Response to 2/15/1977 Letter Requesting a Revision for Technical Spec Figure 3.4-2a) to Provide Additional Margin to Assure Compliance with Appendix G to 10 CFR Part 50

ML18096B497
Person / Time
Site:	Saint Lucie
Issue date:	03/17/1977
From:	Uhrig R E Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-77-82
Download: ML18096B497 (21)

Text

NR C Fo AM 195" (2-7aI U.S.NUCLEAR REGULATORY CC, SSION Ngg DlSTR lBUTlON ron PART 60 DOCKET MATERIAL DOCKET NLIMOE R 5d 334 FILE NUMOER Mr.Victor Stello FROM: Florida Power&Light.,Company Miami, Florida Robert E.Uhrig DATE OF DOCUMENT 3/17/77 OATE RECEIVED 3/21/77 IgLETTE R ABORIGINAL Q.COP Y DESCRIPTION QNOTORI2ED

'ILEIUNCLASSIF IE D PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED Ltr.re our 2/15/77 ltr....trans the following:

ACKNOWLEDGED.DO1lOrpREMOVS PLANT NAtfE: St.Lucie Unit No.1 (2-P)Amdt-to ol/notorized 3/17/77.~.change to tech specs.'.to revise pressure-temperature limits for the first,two effective years of full power operation.,~.(go C,'~S W.nc.r (9-P)'JL FOR ACTION/INFORiVIAT ION ASSXGNED AD: RRQQMH ROJL'CT MA1LG g LXC ASST a.~~C5 BRANC1LC1 PROJECT MANAGER'" LIC ASST~REG FXLE OELD GOSSXCK 6;STAFF MXPC CASE HANAUER 11ARLESS PROJECT MANAGEIKNT BOYD PE COLLXNS llOUSTON PETERSON MELT7.HELTElfES SKOVHOLT LPDS Fk Pr~.~~e TXC NSIC: INTERNAl DIST SYSTEMS SAFETY HEXNEl!AN SCHROEDER ENGINEERXNG HOSii',LXK SXHHEIL~PAWL CK REACTOR SAFE ROSS NOVAK ROSZTOCZY CHECK AT&I SALTZl'fAN RUTHFRG EXTERNAL DISTRIBUTION NAT~LAB'EG VOGIE LA PDR RIBUTION PLANT SYSTEMS TEDEQgO REISE.IPPOLIgO OPERATING REACTORS STELLO OPERATXNG TECH EXSEN11UT gj+0 ME H+EY.E 6M'QQKUMKtLMT

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FL 33101~+0 Ilia k'I migs)f 9'gIH g,k Mm FLORIDA POWER 8(LIGHT COMPANY'arch 17, 1977 L-77-82 Director of Nuclear Peactor Regulation Attention:

Mr.Victor Stello, Director Division of Operating Reactors U.S.Nuclear Regulatory Commission Washington, D.C.20555

Dear Mr.Stello:

Be: St.Lucie Unit 1 Docket No.50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 A letter from your staff dated February 15, 1977 requested that, we revise our pressure-temperature limits for the first 2 effective years of full power operation (Technical Specification Figure 3.4-2a)to provide additional margin to assure compliance with Appendix G to 10 CFR Part 50.We have studied several references (SRP 5.3.2, BTP MTEB No.5-2, and Appendix G to 10 CFR Part.50)dealing with fracture toughness requirements and have developed a new curve with which to replace Figure 3.4-2a.Our new curve conservatively depicts operating conditions for up to 5 effective years of full power operation.

We propose that our new curve be approved for use in place of the current Figure 3.4-2a.Xn accordance with 10 CFR 50.30, we hereby submit three (3)signed originals and forty (40)copies of our request, to amend Appendix A of Facility Operating License DPR-67.The changes are described below and shown on the accompanying Technical.

Specification'pages bearing the date of this letter in the lower right hand corner.Pa e 3/4 4-23a A new Figure 3.4-2a is provided entitled"Reactor Coolant System Pressure Temperature Limitations for up to 5 years of Full Power Operation".

Page 3/4 4-23b The title of Figure 3.4-2b is revised to read"Reactor Coolant System Pressure Temperature Limitations for up to 10 Years of Pull Power Operation".

~7+'QIQ/42 PEOPLE...SERVING PEOPLE

'El ll I P g I l l r E'I il Director of Nuclear Reactor Regulation Page Two March 17, 1977 Page-2-Pa e 3/4 4-23c The title of Figure 3.4;2c is revised to read"Reactor Coolant System Pressure Temperature Limitations for up to 40 Years of Full Power Operation".

The proposed changes have been reviewed by the St.Lucie Facility Review Group and the Florida Power&Light Company Nuclear Review Board.They have concluded that it does not involve an unreviewed safety question.A safety evaluation is attached.Very truly yours, Robert E.Uhrig Vice President REU/MAS/cpc Attachment cc: Mr.Norman C.Moseley, Region II Robert Lowenstein, Esquire F/1 0,~, t I~~I r--=-I I'~~~I~I I.I I.I I I I I"QQ00 t I-I~=,~~i I~i,.p QQQ I--~-l t I~, I'MINIMUM PRESSURE TEMPERATURE FOR:" I~I I*CRITICAL OPERATXOiV OF CORE i ,**NON-CRITICAL OPERATXON OF CORE-'"I~I~~I~LOWEST'SERVICE TEMPERATURE I~I I SYSTEM HYDRO-:-~~I I I~I I I'I I i~CO~'-I I't i'~HEATUP**[COOLDOHN**: I*ji'~~~I~I~~I-I.i~~~I~~~I~)~~g~I~~~I~'-l~HEATUP I I g~I~t I~~~!COOLDOWN*:...~~~, i~t,i I I*~~t'-~, l~t'I~-I~I~I~l'-2000~.I 1, I I~4~~I'I~'I~+I~ti I~I~I j~'-F..~g~boo'n.""'I'-"'-~I'I~~~~~~~~~~~~~I I o)".~~~I~~,.t%00~'-'I.~-'I i~~IW4 I~I'l I~t~~~~~~r~~I I~R~~~I~~~'~)~.I:I"'I~~~~-;N 1-REACTOR VESSEL BELTLINE MATERIAL IViITXAL RT 5 F I 2-REACTOR VESSEL BELTLINE MATERIAL.5 YEAR RT SHXFT~95 F NDT OTE-I-~.~I I~~~I.~I ,...NOTE.~l~I'-~I~" I"4 l~OTE 3.-REMAINING PRESSURE BOUNDARY MAXIMUM RT~50 F-..N i'I'---+Oo i I~t I i~'~I.I I;.I':!: 'I.~'t I~PRESSURE FOR SDC OPERATION':..'-::j:-

.:i 800:~~o:,~pp;+ere I REACTOR COOLANT TEMPERATURE T, F W W"l: j'.j'...'.FIGURE 3.4-2a..:.

~I t yao~~I IiIDXCATED I ST.LUCXE'NIT 1*I~~t~=.I t~I 3/4 4-23a 3/17/77 REACTOR COOLANT SYSTEM PRESSURE T~ERATURE LIMITATIONS:-'

FOR UP IO 5 YEARS OF FULL POWER OPERATION 4 I 60!!:: ti'.t t:tt Iiii lt~I i~il~~3200 It."~I~I~~~IIP~~~~'~~~i~~~~I~I~~~ti:~~~~: I::~: MINIMUM PRESSURE TEMPERATURE FOA:;:..'l CRITICAL OPERATION'OF CORE.NON.CRITICAL OPERATION OF CORE~~2800 2400~I!~~~~fi!i!I i~HR ptt d i tft: II~~~~~~~~~~~11 LOWEST SERVICE TEMPERATUR Pit i M~I~~P\E~~i~~i~~~t'YSTEM HYDRO t~".i I~l'HEATUP i".'".::;: COOLOOWN"::

~~HEATUP'.COOLOOWN~~~~~~~~~~~~~~~~~~~~~~~~~~~~tu lC t~~M~J I~I~~~I~'P*~r>>>>~~t~~~~~2000 1600 I~~~~I 1200 400~>>tt'~!~~"~~~I~~.=+NOTE 1-: iNOTE 2--I'OTE 3-~I~~REACTOR VESSEL 6ELTLINE MATERIAL:::-':

INITIAL RTNo T REACTOR VESSEL 6ELTLINE MAT RIAL~~10 YEAR RTNoT SHIFT~135 F AEMAINING PRESSURE BOUNDARY MAXIMUM RTOT 50'F~~~0~~~;~~~~Itf;~i~i t ft!" lA1XliViUMPRFSSURE

...:: FOR SOC OPERATION<::I"""'-'-'!"" I""!"-I"" Iti M tti ft~~~l~0 100 200 300 400 500 INDICATED AEACTOA COOLANT TEMPERATURE Tc F FIGURE 3.4.2b Itesctor Coo!ant SYstem Pressure Temperature Limitations for up to IO Years of Full Power Operation ST.LUG IE-UNIT 1 3(4 4-Z3b 3/17/77

3600 2800 I~I~~It ta~~I:If LOWEST"" SERVICE, t I TEMPERATURE pa~:tl I~: "f a LL-'.t" tet~~~~~~~~I~: ttat mt SYSTEM HYDRO~~:;NOTE 1-REACTOR VESSEL BELTLINE MATERIAL~INITIAL Rior ea 5 F:I NOTE 2-REACTOR VESSEL BELTLINE MATElIIAL' t~k 40 YEAR RTN0T SHIFT Ra 225 F:: NOTE 3-REMAINING PRESSURE BOUNDARY MAXIMUM RTNgT 50 F Paae PIPPt~a t amtt~'a~g~~~iLI Ip~~RRRC Lla ttmt'ltt';I fa:I~~~I~sate t::t~~~I I I a.t ttta~~~isfa~~I aa~Itta~~I~~I~~I~~2400'i~I~~~~~~t~~~'~~~I~~I t e HEATUPm~~I COOLDOWN HE ATUP~~~P CO 2000 L m I~>>I I=&Wf OL N DON CO~~~I tt: 1600 L I~I~I I~'~~1200~I 800\~<<I~r~~I~~w~~~~I am~400 0~a ftt>~L aa Ltff~~\~a I4IAXIr4urut PRESSURE: "j FOR SDC OPERATION t I:: at MINIMUM PRESSURE TEMPERATURE FOR: m CRITICAL OPERATION OF CORE,'m NON CRITICAL OPERATION OF CORE:::f::::-::I::j:~.'::.'.I:L::-:

.i.:i:'.."':t'.['tt:

"~:):::::"':::::~::::::!I tj Iftj Etfe 0 100 200 300 400 500 INDICATED REACTOR COOLANT TEMPERATURE T~F FIGURE 3A-2c Reaetar Caalaat System pressure Temperature Llmltatlaas for up to 40 Years of Ful I Power Operation ST.LUCIE-UijIT 1 3/4 4-23c 3/17/77

SAFETY EVALUATION

1.0 Introduction

This evaluation supports proposed changes to the St.Lucie Unit 1 Pressure-Temperature curves (Figures 3.4-2a, 3.4-2b, and 3.4-2c).2.0 Discussion

2.1 Figure

3.4-2a Criteria presented in paragraph 2.2.2 of Branch Technical Position 5-2 (Fracture Toughness Require-ments)lead to the following equation: RTNDT z.nitial)+RTNDT (shift due to service)>RTNDT (maximum from remaining pressure boundaries)

+50'F This relationship has been used to develop a new Technical Specification Figure 3.4-2a.The new curve is applicable for up to 5 years of full power operation.

A minimum RT shift of 95'F is necessary to satisfy Equation (1).A 95'F shift is midway between the 55'F shift of the current Figure 3.4-2a and the 135'F shift of Figure 3.4-2b.To develop a new Figure 3.4-2a that will satisfy Equation (1), the 10-year curves of Figure 3.4-2b were shifted 40'F to the left.This technique is justified based on paragraph 3c of section III to Standard Review Plan 5.3.2 (Pressure-Temperature Limits).Information from Chapter 5 of the FSAR was used to determine the service time for which a 95'F shift will be applicable.

a)The pertinent chemical composition of the weld in the beltline region was obtained from Table 5.2-4A on page 5.2-14:.23 weight 8 Cu.013 weight 0 P b)The end-of-life RT shift and the end-of-life fluence were obtainect from Sections 5.2.3.5.5.NDT (page 5.2-18)and 5.4.4 (page 5.4-8): end-of-life RTNDT shift=225'F end-of-life fluence=1.91x10 n/cm 19 2 SAFETY EVALUATION (Continued) c)An equation relating RT D , chemical composition, and fluence was obtainecPErom Regulatory Guide 1.99 (Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials):

RT DT (shif t)=[40+1000 (8 Cu-0.08)+5000 (SP-0.008)

)'t-]1/2 1019 or, (-)z 10=f (n/cm)NDT 19 2 215 RTNDT (F)225 135 95 55 f (n/cm)2 1.9lxlO 3.94xlo 1.95xlo 0.65xlO time (yrs.)40 10 The attached figures show the pressure-temperature curves for RTNDT=95'F and a semi-logarithmic plot of fluence vs.service life.The service life plot shows that, after 5-1/2 years of full power operation, the vyisel surface has been exposed to a fluence of 1.95xlO n/cm Thus, the new pressure-temperature curves conservatively depict operating conditions for up to 5 years of full power.operation.

2.2 Fi ures 3.4-2b and 3.4-2c'Since the pressure temperature curves represent an upper boundary on service life, the titles are revised to read"up to 10 Years" and"up to 40 Years" instead of"2 to 10 Years" and"10 to 40 Years", respectively.

3.0 Conclusions

Based on these considerations, (1)the proposed change does not increase the probability or consequences of accidents or malfunctions of equipment important to safety and does not

SAFETY EVALUATION (Continued) reduce the margin of safety as defined in the basis for any technical specification, therefore, the change does not involve a significant hazards consideration, (2)there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3)such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

j200)---'.28o I~I l I J l'.~r l)2000.~~'~.g s)N'gloo v...i I I v-)v~)!~~~I I'v v!v~!I!, LOWEST'SERVICE!TEtPERATURE

)v'F l I'I I)SYSTEM HYDRO I-I~HEATUP**j l~j'OOLDOL)'N

+*~I I~HEATUP*(t,~COOLDOWN*!.-)~v I~~v~~I v l...>~~j v I"l~I-g I~.)I I~I~-'INIMUM PRESSURE TEi4lPERATURE FOR'I~*CRITICAL OPERATIOiV OF CORE ,**NON-CRITICAL OPERATION OF CORE'~ul-I%0~~~v~~~~~v~~~'v v!~evvvt v v'!Y v.~v v v v~~A'I v~~!" l I-'"-N I~Av OTE 1-ACTOR VESSEL BELTLINE MATERIAL INITIAL RT~5 F I~v.AN NOTE 3-REMAINING PRESSURE BOUNDARY MAXIMUM RT=50 F NDT I!~OTE 2-REACTOR VESSEL BELTLINE MATERIAL 5 YEAR RT SHIFT~95 F l I l)!I I ST.LUCIE'"MAXIMM PRESSURE FOR SDC OPERATION;

/00 g.Oo.gpp~a,.geo INDICATED REACTOR CO LANT TEMPERATURE TC'~.)UNIT 1~~j'REACTOR COO)ART SYSTLV PRESSURE T HPERATURE LI))TTATTQvgS

~-,.-FOR UP TO 5 YEARS OF FULL POMER OPERATION I

VESSEL MALL.SURFACE FLUENCE=1.95x10 Nf'CM 18 RT 95oF NDT/o 2p 30 SERVICE LIFE (YEARS)FAST NEUTRON FLUENCE (E>l~ifEV)

AS A, FUNCTION OF SERVICE LIFE

~'

STATE OF FLORIDA))COUNTY OF DADE)ss ADOPT , being first duly sworn, deposes and says: That he is Executive Vice Presi n Light Company, the Lz.censee herein;~of Florida Power That he has executed the foregoing document;that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that.he is authorized to execute the document on behalf of said Licensee.E.A.Adomat sworn to before me this ,,<<q ub's'ex~bed and reTARY<~-UBLIC, in and for the County of Dade, S h~ate"".'o f Florida<lrIIIÃ4"~"" NOTARY PUBLIC STAG Of fLORIDA A1 LARQ MY COMMISSION EXPIRES NOV.30 1979 My commission expires: BoIeEo THRU a~ERAL INS.UNDERwRIIERS

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