ML17341A918

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Tech Specs for Insp of Steam Generators,Turkey Point Units 3 & 4, Technical Evaluation Rept
ML17341A918
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 01/31/1982
From: Stevenson J
EG&G, INC.
To: Donohew J
Office of Nuclear Reactor Regulation
References
CON-FIN-A-6429 EGG-EA-5743, NUDOCS 8203040588
Download: ML17341A918 (18)


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FOAM EQXG4Sb Idaho. Inc.

(Aev. 11 TPj INTERIM REPORT Accession No.

Report No EGG-EA-5743 Contract Program or Project

Title:

Selected Operating Reactor Issues Program (III)

Subject of this Document:

Technical Specifications for the Inspection of Steam Generators, Turkey Point, Unit Nos. 3 and 4 Type of Document:

Technical Evaluation Report Author(s):

J. A. Steverson Date of Document:

January 1982 Responsible NRC Individual and NRC Office or Division:

J. N. Donohew, Division of Licensing This document was prepared primarily for preliminary or internal use. It has not received full review and approval. Since there may be substantive changes. this document should not be considered final.

EGB G Idaho. Inc.

Idaho Falls, Idaho 83415 Prepared for the U.S. Nuclear Regulatory Commission Washington, O.C.

Under OOE Contract No. OE-AC07-76I001570 NRC FIN No A6429 INTERIM REPORT

/ I j TECHNICAL SPECIFICATIONS FOR THE INSPECTION OF STEAM GENERATORS TURKEY POINT, UNIT NOS. 3 ANO 4 Docket Nos. 50-250, 50-251 January 1982 by J. A. Steverson Reliability and Statistics Branch Engineering Analysis Division EG&G Idaho, Inc.

ABSTRACT This report reviews the Turkey Point, Unit Nos. 3 and 4 technical specifications for stean generator inspection.

FORD+D This report is supplied as part of the "Selected Operating Reactor Issues Program (III)" being conducted for. the U.S. Nuclear Regulatory Comnission, Office of Nuclear Reactor Regulation, Division of Licensing, by EG&G Idaho, Inc., Reliability and Statistics Br anch.

The U.S. Nuclear Regulatory Commission funded the work under the authorization, MR 20 19 02 06, FIN No. A6429.

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TECHNICAL EVALUATION REPORT TECHNICAL SPECIFICATIONS FOR THE INSPECTION OF STEAM GENERATORS K PO N UN NO . 3 ANO

1. 0 INTROOUCTION Turkey Point steam generator s have been inspected according to special license conditions imposed originally by Amendment 20, dated Oecember 3, 1976, for Unit '4 and by Amendment 22, dated January 14, 1977, for Unit 3.

Thus, technical specifications for the inservice inspection of the steam 1

generator tubes were not required. By letter, dated July 1, 1981, the NRC requested Turkey Point 3 and 4 review their submittals and appropriately modify them, using as a guide the technical specifications for steam gener-ator inspection provided by the NRC.

On Oecember 18, 1981, Florida Power and Light (FPEL) submitted pro-2 posed changes to their technical specifications (TS). The following discussion evaluates the proposed Turkey Point TS and notes any differences existing between them and the NRC model TS.

2.0 OISCUSS ION ANO EVALUATION Turkey Point, Units 3 and 4 are three loop Westinghouse PWR Plants.

The specific sections of the Westinghouse Standard Technical Specifica-tions that apply to this task are as follows:

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.6 STEAM GENERATORS 3/4.4.7 REACTOR COOLANT SYSTEM LEAKAGE The licensee proposed the following changes and incorporations to their technical specifications. First, Specification 3.1.3.6 was revised and

3. 1.3.g was added to incorporate limiting conditions for operation regarding primary-to-secondary leakage through steam generator tubes. This satisfies requirements 3.4.7.2.c and 3.4.7.2.d in the NRC standard TS. Secondly, a

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steam generator inspection program was added to the licensee's section on Reactor Coolant System Inservice Inspection. The progr'am is in Section 4.2.5, Steam Generator Inspection, and in Tables 4.2-2 and 4.2-3 of their proposed TS and coincides with Section 3/4.4.6, Steam'Generators, and with Tables 4.4-1 and 4.4-2 of the Mestinghouse Standard TS.

Also in the steam generator inspection p~ogram, the Mestinghouse Stan-dard TS in Section 4.4.6.3.a, Inspection Frequencies, require the first inservice inspection to be per formed after six effective full power nnnths but within 24 calendar months of initial criticality. The licensee's cor-responding requirem nt in Section 4.2.5.3.a, requires the first inservice inspection to be performed after the first refueling following initial criticality or replacement of steam generators (whichever is later).

3. 0 CONCLUS ION The proposed TS submitted by FPQ. for Turkey Point, Units 3 and 4 included revisions and/or additions regarding (1) primary-to-secondary leakage through steam generator tubes, and (2) a steam generator inspection program. A basis for the steam generato~ inspection was also added to the specification.

The TS proposed by Turkey Point are in agreement with the Westinghouse Standard TS with two exceptions. The pr'eceeding evaluation noted (1) an omission in the Turkey Point TS concerning the inspection of the fir st sample of stean generator tubes, and (2) a difference in the timing of the first inservice inspection of a steam generator.

4. 0 R EFERENCES
1. NRC letter, S. A. Varga, to FP&L, R. E. Uhrig, dated July 1, 1981.
2. FP5L letter, R. E. Uhrig, to NRC, D. G. Eisenhut, dated December 18, 1981.
3. Standard Technical Specifications for Westinghouse PMRs, NUREG-0452, Rev. 3, Fall 1980.

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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS. 50-250 AND 50-251 FLORIDA POWER AND LIGHT COMPANY NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 81 to Facility,Operating License No. DPR-31, and Amendment No. 75 to Facility Operating License No. DPR-41 issued to Florida Power and Light Company'(the licensee), which revised Technical Specifications for operation of Turkey Point Plant, Unit Nos. 3 and 4 (the facilities) located in Dade County, Florida. The amendments are effective as of the date of issuance.

The amendments incorporate the steam generator inservice inspection requirements into the Techncial Specifications. These specifications replace Facility Operating License No. DPR-31 condition 3.E for Unit 3 effective as of the date of this amendment and Facility Operating License No. DPR-41 condition 3.D for Unit 4 effective as of the date of completion of the steam generator replacement in Unit 4, The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has, made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments. Prior public notice of these amendments has not required since the amendments do not involve a significant hazards consideration.

7590-01 The Commission has determined that the issuance of these amendments will not result in any significant environmental impact'nd that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration 4

and environmental impact appraisal need not be prepared in connection with issuance of these amendments.

For further details with respect to this action, see (1) the application for amendments dated December 18, 1981, (2) Amendment Nos. 81 and 75 to License Nos. DPR-31 and DPR-41, and (3) the Commission's related Safety Evaluation. All of these items are available for public inspection at the Commission's Public Document Room, 1717. H Street, N.W., Washington, ll D.C.

and at the Environmental and Urban Affairs Library, Florida International University, Miami, Florida 33199. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Director, Division of Licensing.

Dated at Bethesda, Maryland, this 24th day of March, 1982.

F R THE NUC EGULATORY COMMISSION arga, C f Operating Reactors nch 81 Division of Licensing

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~1 DI STRI B UTI ON Dockets MDunnel fel d NRC PDR Gray File L PDR J

MAR 17 1982 NSIC Docket Nos. 56~250 ORB¹l Rdg and 50-251 DEisenhut IE-2 ACRS-10 Dr. Robert E. Uhrig, Vice President Q 8FQQ~~ TBarnhart-8 Advanced Systems and Technology

~ 4 LSchneider g~~ 8 DBrinkman Florida Power and'ight Company ~p jgap~

OPA Post Office Box 529100 '~@~ee "'

Hiami, Florida 33152 Tlpj RDiggs 6 NGrotenhuis

Dear Dr. Uhrig:

l CParrish

~ 1 ASLAB The Commission has issued the enclosed Amendment Ho. 80 to Facility Operating License No. DPR-31 and Amendment No. 74 to Facility Operating License No.

DPR-41 for the Turkhy Point Plant Unit Hos. 3 and 4, respectively. The amendments consist of changes to the Technical Specifications in response to your application transmitted by letterrdated IIay 14, 1981, as supplemented November 23, 1981 and January 28, 1982.

These amendments revise the Technical Specifications to specify new power distribution limits for base load and radial burndown operation.

Itle have received you letter dated March 15, 1982 which satisfied the curr ent requirements of Technical Specification 6.9.3 for Unit 3. Such a r eport is not necessary for Unit 4 at this time because PT is not less than 1.

Ile have found it necessary to make changes in certain of the Technical Specifications. Ite have discussed the changes with your staff. They found the changes acceptable and the chhn)es have been incorporated.

Copies of the Safety Evaluation and the Notice of Issuance are a)sd enclosed.

Sincerely,

-D~GINAL SZCNK5 tlarshall Grotenhuis, Project Manager Operating Reactors Branch ¹1 Division of Licensing

Enclosures:

l. Amendment Ho. 80 to DPR-31
2. Amendment No. 74 to DPR-41
3. Safety Evaluation
4. Notice of Issuance  %

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OFFICE/

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DISTRIBUTION Dockets ASLAB NRC PDR Gray File L PDR MDunnenfeld TERA Docket Nos.60-260 NSIC and 50-251 ORBkl Rdg DEisenhut OELD IE-4 ACRS-10 GDeegan-8 LSnyder DBrinkman OPA RDiggs

Dear Dr. Uhrig:

MGrotenhuis CParrish The Commission has iqqued the enclosed Amendment No. to Facility Operating License f(o. DPR-31 and Amendment No. to Facility Operating License No.

DPR-41 for the Turkey Point Plant Unit Nos. 3 and 4, respectively. The amendments consist of changes to the Technical Specifications in response to your application transmitted by letter dated May 14, 1987, as supplemented November 23, 1981 and January 28, 1982.

These amendments revise the Technical Specifications related to base, load and radial burndown.

Copies of the Safety Evaluation and the Notice of Issuance are alsoeenclosed.

Sincer ely, Marshall Grotenhuis, Project Manager Operating Reactors Branch 01 Division of Licensing

Enclosures:

'1. Amendment No. to DPR-31

2. "Amendment No. to DPR-41
3. Safety Evaluation
4. Notice of Issuance cc v(/enclosures:

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Robert "=. Uhrig Florida Power and Light Company CC: fir. Robert Lowenstein, Esquire her. Jack Shreve Lowenstein, Newman, Reis and Axelrad Office of the Public Counsel 1025 Connecticut Avenue, N.M. Room 4, Holland Building Sui te'1214 Tallahassee; Florida 32304 Vashington, D. C. 2"-035 Admini strator Environmental and Urban Affairs Library Department of Environmental Florida International University Regulation Miami, Florida 33199 Power Plant Siting Section State of Florida Hr. t<orman A. Coll, Esquire. 2600 Blair Stone Road Steel, Hector and Davis Tallahassee, Florida 32301 1400 Southeast First, National Bank Building James P. O'Reilly Miami, Florida 33131 Regional Administrator - Region II U. S. Nuclear Regulatory Commission h1r. Henry Yaeger, Plant Manager 101 Marietta Street - Suite 3100 Turkey Point Plant Atlanta, Georgia 30303 Florida Power and L~ht Company P. 0. Box 013100 Miami, Florida 33101 Honorable Dewey Knight County tianager of Metropolitan Dade County t'li ami, Florida 33130 Bureau of Intergovernmental Relations 560 Apalachee Parkway Tallahassee, Florida 32304 Resident Inspector Turkey Point nuclear Generating Station U. S. nuclear Regulatory Commission Post Office Box 1207 Homestead, Florida 33030 Regional Radiation Pepresentative EPA Region IV 345 Courtland Street, H.M.

Atlanta; Georgia 30308

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