ML17340B061

Requests Amends to Licenses DPR-31 & DPR-41 to Specify Scope of Steam Generator Insp Program,Acceptance Criteria & Reporting Requirements.Request Supplements 810402 Request

ML17340B061
Person / Time
Site:	Turkey Point
Issue date:	04/17/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
L-81-172, NUDOCS 8104270260
Download: ML17340B061 (10)

Text

REGULA JR A Y LNFORHATION 0 I STRI8U TIDIES SYSTEM (RIDS)

ACCESSION FACIL:5 0

<< 'rkey NaR;8}04270260 251 Point urKey Point Duc.nATE.:

Planti Unit chianti Unit 8}/O~/}7 3E OE Florida Florida NOTARIZED: YES Power and Light Power and Lignt C

C DOCKET 05000250 0500025}

AU AUTHOR At FILIATION UHRIGR R ~ E ~ Florioa Power 8 Light Co ~

RECIP ~ NAME RECIPIENr AFFILIATION EISENHUTED ~ G ~ Division of Licensing

SUBJECT:

Requests amends to Licenses DPR 31 h DPiA'} to specify scooe ot .steam generator insp program<acceptance criteria reoorting requirements, Request supplements 8}0402 reauest.

DISTRIBUTION CODE: AOO IS COPIES RECEIVED:LTR Ll ENCL + SIZE:

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TITLE: Gener al Distr itiution for af ter Issuance

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COPIFS RECIPIENT of Operating License COPIES IO CODE/NAME i.TTR FNCL ID CODE/NAME LTTR ENCL ACTION: VAIiGAE S ~ OQ }3 13 INTERNAL: D/OIREHUH FACOS 1 1 DIRE DIV OF LIC 1 1 Iah, Oo 2 NRC PDR 02 1 1 OELD i} 1 0 0 AS ESS 8R 10 1 0 RAD AS>lT BR 1 1 G 01 1 = 1 EXTERNAL: ACRS 09 }0 16 LPDR 1 1 Nslc 05 1 1 II TOTAL NU'ABER OF COPIES REQUIRED: LTTR 40 ENCL 38

April 17, 1981 L-81-172 s,cO Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, D'irector Division of Licensing U.S. Nuclear Regulatory Commission Washington D.C. 20555

Dear Mr. Eisenhut:

Re: Turkey Point Units 3 5 4 r g Docket Nos. 50-250 and 50-251 t Proposed License Amendments In accordance with 10 CFR 50.30, Florida Power 8 Light Company submits herewith three signed originals and forty copies of a request to amend Facility Operating Licenses DPR-31 and DPR-41. This request supplements our request of April 2. 1981 (L-81-144).

The proposed amendment is described below and shown on the accompanying pages bearing the date of this letter in the, lower right hand corner.

The License conditions have been modified to specify in the license the scope of the steam generator inspection program and acceptance crit'eria and the reporting requirements. This amendment is administrative in nature since it does not change the technical content of the inspection and plugging program.

The proposed amendment has been revi.ewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board.

We have determined that since this request supplements the previous request but involves a duplicate amendment, the request should be classified as a Class I Amendment pursuant to 10 CFR 170. Accordingly, a check for $ 400 is enclosed.

Vice President Advanced Systems and Technology gooi REU/JEM/mbd 5 Attachment ~h cc: Mr. James P. O'Reilly, Region II ~/z~:

Harold F. Reis, Esquire g psn. nn Q t.k 2 > .Q QlcrQ P

DPR-31 Page 3 B. Tech~nical S ecificaciona The Technical Specifications contain~d in Appendices A and B, as revis~d through Amendment No. 62 are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications..

C. ~Re orts FPL shall issue certain reports to the NRC in accordance with the requirements of the Technical Specifications.

D. Records FPL shall originate and maintain facility operating records in accordance with the requirements of the Technical Specifications.

E. Steam Generator Inspections

1. After operation of six equivalent full power months from the last inspection of all three steam generators Turkey Point Unit 3 shall be brought to the cold shutdown condition and al 1 three steam generators shall be inspected unless: (1) an inspection of the steam generators is performed within this period, or (2) an extention is granted by the NRC to authorize continued operation beyond the authorized period of operation. Any request for continued operation must be submitted at least 45 days prior to the expiration date of the authorized period of operation. For the purpose of this requirement, equivalent operation is defined as operation >>ith the reactor coolant at a temperature greater than 350"F.

2. Reactor coolant to secondary leakage through the steam generator tubes shall be limited to 0.3 gpm per steam generator. tlith a steam generator tube leakage greater than this limit. the reactor shall be brought to the cold shutdown condition within 24 hours and an inspection of the leaking steam generator shall be performed.

3. The concentration of radioiodine in the reactor coolant shall be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients.

4. If primary to secondary leakage attributable to the denting phenonmena is detected in 2 or more tubes during any 20 day period an inspection of the leaking steam generator shall be performed by the licensee.

5. The inspection and plugging results from 1, 2, or 4 above shall be submitted to the NRC no later than 14 days following the return to power operation. Any unusual results from the denting inspections shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. It in the inspections performed under regulatory position C.5 of Regulatory Guide 1.83, more than 10%

of the total tubes inspected have detectable wall penetration (>205) or more than three of the tubes inspected exceed the plugging limit, the inspection results shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4/17/8l

DPR-31 Page 4

6. The scope of the steam generator inspections (including eddy current, gauging and visual inspection) and tube plugging criteria shall be consistant with FPL letter L-80-412 dated December 18, 1980. The scope of the program shall be increased as appropriate to reflect operating experience and/or analysis.

7. Prior to resumption of power operation following inspections per 1, 2, and 4 above the licensee shall perform a 'safety analysis per 10 CFR 50 Section 59.

F. The licensee shall maintain in effect and fully implement all provisions of the Commission-approved phvsical securitv oian, includinq amendments and changes made pursuant to the authority of 10 CFR 50.54 (p). The approved security plan documents, witheld from public disclosure pursuant to 10 CFR 2.790(d), collectivelv titled "Turkev Point Plant Unit Nos. 3 and 4 ohvsical Securitv Plan". dated October 18. 1979. as sunnlemented Februarv 20. 1979.

G. The licensee mav nrnce~d wi th and is reaui r~d to orovide a schedule for and to comolete the modifications indentified in Paraaraohs 3.1.1 throuoh

3. 1.19 nf the NRC s Fire Pr nt~rtinn Safetv Evaluation. dated March 21, 1979 for the facility. These modifications are to be comoleted orior to December 1980. If anv modifications cannot be cnmnleted on schedule the licensee shall submit a reoort exolaininq the circumstances toaether with a revised schedule.

In addition. the licensee shall submit the additional information indentified in Sections 3.1 and 3.2 of the related Safetv Evaluation in accordance with the ~chedule rnnt~incd thar> in ln tha avant these dates for submittal cannot be met, the licensee shall submit a rennrt.

explaining the circumstances, together with a revised schedule.

The licensee is requi red to develop and implement the administrative controls which are consistent with the licensee's letters of August 28 and November 7, 1978 within three months from the date of this amendment.

H. Safeguards Contingency Plan The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Safequards Contingency Plan, including amendments and chanqes made pursuant to the authority of 10 CFR 50.54(p). The approved Continqency Plan consists of documents witheld from oublic disclosure oursuant to 10 CFR 2.790(d) and identified as "Turkev Point Plant Safequards Continaencv Plan" dated June 17, 1980 and submitted oursuant to 10 CFR 73.40. The Continaencv Plan shall be fullv imolemented. in accordance with 10 CFR 73.40(b). within 30 davs of this aonroval.

4/17/8l

DPR-41 D. Steam Generator Inspections Page 4 After operation of six equivalent full power months from the last inspection of all three steam generators, Turkey Point Unit 4 shall be brought to the cold shutdown condition and all three steam generaters shall be inspected unless" (1) an inspection of the steam generators is performed within this period, or (2) an extention is granted by the NRC to authorize continued operation beyond the authorized period of operation. Any request for continued operation must be submitted at least 45 days prior to the expiration date of the authorized period of operation. For the purpose of this requirement, equivalent operation is defined as operation with the reactor coolant at a temperature greater than 350'F.

2. Reactor coolant to secondary leakage through the steam generator tubes shall be limited to 0.3 gpm per steam generator. With a steam generator tube leakage greater than this limit, the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and an inspection of the leaking steam generator shall be performed.

3. The concentration of radioiodine in the reactor coolant shall'be limited to 1.0 microcurie/gram during normal operation and to 30 microcuries/gram during power transients.

4 If primary to secondary leakage attributable to the denting phenonmena is detected in 2 or more tubes during any 20 day period an inspection of the leaking steam generator shall be performed by the lic'ensee.

5. The Metal Impact Monitoring System (MIMS) shall be continued in operatio'n with the capability of detecting loose objects. If the MIMS is out of service in other than cold shutdown or refueling mode of operation, this fact shall be reported to the NRC. Any abnormal indications from the MIMS shall also be reported to the NRC by telephone by the next working day and by a written evaluation within two weeks.

6. Following each startup from below 350'F, core barrel movement shall be evaluated using Neutron Noise Technique.

7. The inspection and plugging results from 1, 2, or 4 above shall be submitted to the NRC no later than 14 days following the return to power operation. Any unusual results from the denting inspections shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If, in the inspections performed under regulatory position C.5 of Regulatory Guide 1.83, more than 105 of the total tubes inspected have detectable wall penetration (>205,) or more than three of the tubes inspected exceed the plugging limit, the inspection results shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

8. The scope of the steam generator inspections (including eddy current, guaging and visual inspection) and tube plugging criteria shall be consistant with FPL letter i-80-412 dated December 18, 1980. The scope of the program shall be increased as appropriate to reflect operating ri expe ence and/or anal ys i s.

9. Prior to resumption of power operation fol lowing inspections per 1, 2, and 4 above the licensee shall perform a safety analysis per 10 CFR 50 Section 59.

4/17/81

STATE OF FLORI DA )

) ss.

COUNTY OF DADE )

Robert E. Uhrig, being first duly sworn, deposes and says:

That he is a Vice President of Florida Power & Light Company, the Licensee herein; 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.

Robert E. Unrig Subscribed and sworn to before me this

~clay of NOTARY PUBLIC, and for the county of Dade, State of Florida I'

1 M'/ CdiTi l&ldrt Ptf8$ CCidd.r commission expires:

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