ML18096B497

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:	Robert E. Uhrig 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 NLIMOER 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 IgLETTER ABORIGINAL Q.COP Y DESCRIPTION QNOTORI2ED

'ILEIUNCLASSIFIE 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.,

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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:

INTERNAlDIST SYSTEMS SAFETY HEXNEl!AN SCHROEDER ENGINEERXNG HOSii',LXK SXHHEIL

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LAB'EG VOGIE LA PDR RIBUTION PLANT SYSTEMS TEDEQgO REISE.

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'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

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Director of Nuclear Reactor Regulation Page Two March 17, 1977 Page 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

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LUGIE - UNIT 1

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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 (shift) = [40 + 1000 (8 Cu-0. 08)

+ 5000 (SP-0.008)

) 't

] 1/2 1019 or,

(

) z 10

= f (n/cm

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NDT 19 2

215 RTNDT ( F) 225 135 95 55 f(n/cm

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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.

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STATE OF FLORIDA

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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 re TARY<~- UBLIC, in and for the County of Dade, S h~ate"".'of Florida

<lrIIIÃ4"~""

NOTARY PUBLIC STAG Of fLORIDA A1 LARQ MYCOMMISSION EXPIRES NOV. 30 1979 My commission expires:

BoIeEo THRU a~ERAL INS. UNDERwRIIERS

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