ML013330436

Issuance of Amendments 13 and 12, Incorporating Into Turkey Point Nuclear Generating Units 3 and 4 TS Changes to Reporting Requirements

ML013330436
Person / Time
Site:	Turkey Point
Issue date:	11/26/1975
From:	Lear G Office of Nuclear Reactor Regulation
To:	Robert E. Uhrig Florida Power & Light Co
References
Download: ML013330436 (28)

Text

NRC PDR SVarga Local PDR CHebron November 26, 75 ORB Reading AESteen Attorney, OELD DEisenhut Docket Nos. ,-250. OI&E (3) ACRS (16) and 50-250' NDube bcc: TBAbernathy BJones (w/4 encls) JRBuchanan J4cGough JSaltzmen, OAT (w/o Tech Specs)

WEIlliott GLear Florida Power and Light Company CParrish AmfN: Dr. Robert B. Uhrig Vice President KRGoller P. 0. Box 013100 SKari (w/o Tech Specs)

Miami, Florida 33101 BScharf EPLicensing er Asst.

Gentlemen: Gent Iemen:TJCart TIe Commission has issued the enclosed Amendment No. 13 to Facility Operating License No. DPR-31 and Amendment No. 12 to Facility Operating License No. DPR-41 for the Turkey Point iNuclear Generating Units 3 and 4.

Those anendments include Change No. 25 to the Technical Specifications, Appendix A, and is in response to your request dated December 20, 1974.

These amendments incorporate into the Turkey Point Nuclear Generating, Units 3 1 4 Technical Specifications changes to the reporting requirements.

Changes to your proposal were necessary to meet our requirements. These have been discussed with your staff. The Technical Specifications are based on Regulatory Guide 1.16, "Reporting of Operating Information Appendix A Technical Specifications", Revision We request that you use the formats presented in the Appendices to Regulatory Guide 1.16, Revision 4, for reporting operating informiation and that you report events of the type described under the section "Events of Potential Public Interest". Instructions for using these reporting formats are contained in Regulatory Guide 1.16 (a copy is enclosed for your use), and AEC report 001-SS-001 titled "Instructions or Preparation of D)ata Bntry Sheets for Licensee Event Report (LER)

File" of which you were previously provided a copy. This report is iodified by umiated instructions dated August 21, 1975 which are enclosed. Co*y requirements are summarized in Regulatory Guide 10.1, "Conpilation of Reporting- Requirements for Persons Subject to NRC Regulations", a copy of which is also enclosed. This guide will assist youl in identifying reports that arc required by the Con-mission's regulations set Forth in Title 10 Code of Federal Regulations but are not]L containedl

..reuain in your Tec']Jical Specifications. Reports that.haare fCJic.at.o required by the regulations have not been repeateil in your Technical St ecifi cions.

C'ie*s or tne related Safety Evaluation and the Federal Register Notice also are enclosed.

Sincerely, OFFICE*-.

OT,

, " al"'r its'h'"7 5........ .. .. ..! . . y . . ........I-G -!e -ar ..., ... ,.................-t

................ I..........

o A-E. 024 U G OperNMENg Reactors Branch #3 Form AEC-318 (Rev. 9-53) AECM 0240 *U.S. GOVERNMENT PRINTiNG OFFICE: 1974.2128-IS6

Enclosures:

1. Amendments Nos. 13 and 12

2. Regulatory Guide 1.16

3. Updated Instructions

4. Regulatory Guide 10.1

5. Safety Evaluation

6. Federal Register Notice cc w/encls:

Mr. Jack R. Newman, Esquire Lowenstein, Newman, Reis & Axelrad 1025 Connecticut Avenue, N. W.

Suite 1214 Washington, D.C. 20036 Environmental & Urban Affairs Library Florida International University Miami, Florida 33199 Mr. Ed Maroney Bureau of Intergovernmental Relations 725 South Bronough Street Tallahassee, Florida 32304 OFFICE*" I I I I CSrmA TA - .1 ............................................ .............................................. ............................................. .............................................. .............................................. ..................... . ................

wnit AE-318 (RevT. 9-53) ALEC*[ 0240 "*u. S. GOVERNMFNT PRINTING OFFICE: 1974-526-166

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555

'FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT NUCLEAR GENERATING UNIT NO. 3" AMENDMENT TO FACILITY OPEPATING LICENSE Amendment No. 13 License No. DPR-31

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Florida Power & Light Company (the licensee) dated December 20, 1974, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulation of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Co=mission's regulations; and D. 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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2. Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Facility License No. DPR-31 is hereby amended to read as follows:

"(B) Technical Specifications The Technical Specificatioils contained in Appendices A and B, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No. 25"

3. This license amendment is effective 30 days from the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION fr George Lear, Chief Operating Reactors Branch #3 Division of Reactor Licensing

Attachment:

Change No. 25 Technical Specifications Date of Issuance: November 26, 1975

UNITED STATES

'CLEAR REGULATORY COMMiSSION*.

WASHINGTON, D. C. 20555 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 12 License No. DPR-41

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Florida Power & Light Company (the licensee) dated December 20, 1974, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth inli0 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the.health and safety'of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; and D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

2. Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B. of Facility License No. DPR-41 is hereby amended to read as follows:

"(B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, as revised by issued changes thereto through Change No. 25"

3. This license amendment is effective 60 days from the date of its issuance.

FOR THE NUCLEAR REGULATORY CO'4IISSION George Lear, Chief Operating Reactors Branch #3 Division of Reactor Licensing

Attachment:

Change No. 25 Technical Specifications Date of Issuance: November 26, 1975

ATTACIMENT TO LICENSE AIMENDMENTS NOS. 13& 12 CHANGE NO. 25 TO THE TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. DPR-31 & DPR-41 DOCKETS NOS. 50-250 AND 50-2SI Replace page i, page ii, page 1-5, page 6-11, page 6-14, and pages 6-16 through 6-27 with the attached revised pages.

TAB LE C: CC' 73..

Section Title lage TECINICAL SPECIFICATIONS 1 DEFINITIONS 1-1 1.1 Safety LLits I-i 1.2 Limiting Safety System Settings 1-i 1.3 Limiting Conditions for Operation 1-.

1.4 Operable 1-1 1.5 Containment Integrity 1-2 1.6 Protective Instruzentation Logic 1-2 1.7 Instrumentation Surveillance 1-3 1.8 Shutdown 1-3 1.9 Power Operation 1-4 1.10 Refueling Operation 1-4 1.11 Rated Power 1-4 1.12 Thermal power 1-4 1.13 Design Power 1-4 1.14 (Deleted) iS-2S 1.15 Power Tilt 1-S 1.16 Interim Limits 1-6 1.17 Low Power Physics Tests 1-6 2 SAFETY LI'ITS AND LIMITIXG SAFETY SYSTEM* SETTINGS 2.1-1 2.1 Safety Limit, Reactor Core 2.1-1 2.2 Safety Limit, Reactor Coolant System Pressure 2.2-1 2.3 Limiting Safety System Settings, Protective Instrm*entation 2.3-1 3 LIMITING CONDITIONS FOR OPERATION 3.1-1 3.1 Reactor Coolant System 3.1-1 Operational Components 3.1-1 Heat Up and Cool Dow-n 3.1-2 Leakage 3.1-4 Maximum Reactor Coolant Activity 3.1-5 Reactor Coolant Chemistry 3.1-6 3.2 Control Rod and Power Distribution Limits 3.2-1 Control Rod Insertion Limits 3.2-1 Misaligned Control Rod 3.2-2 Rod Drop Time 3.2-2 Inoperable Control Rods 3.2-2 Control Rod Position Indication 3.2-3 Power Distribution Limits 3.2-3 In-Core Instrumentation 3.2-7 Axi~al Offset Alarms 3.2-8 3.3 Containment 3.3-1 3.4 Engineered Safety Featbres 3.4-1 Safety Injection and MuR Systems 3.4-1 Emergency Containrent Cooling Systems 3.4-3 Emergency Containment Filtering System 3.4-4 Component Cooling System 3.4-4 Intake Cooling h'ater System 3.4-5 3.5 Instrmmentation .3.5-i 3.6 Chemical and Volume Control System 3.6-1 i

TAB~LE OF C0:,-fiI:*'IS (Continu ,

Ti tle FlCCtrical systems 3.7-1 3.8 3.F 3.9 Radioactive'.-'c:iteriais Release 3.0j- 1 Liquid Wastes 3.S-i Gascous '-'astcs 3. 9-21 3.9-3 3.10 3.10-3 3.11 11iscc~cous l oactive l-,vatcrials Soiurccs 3.11-Is 4 4.1-1 4.1 Oper-ov ioxi 1 Sn.f"ty Rve 4.2 Jkcac.Vo Coolanti Systzc, I% Service Is~to 4 .2-)1 4.3 Reactor Co~lant Sy't:t ý Ihrt), 4.3-1 4.4 4.4-1 ln~egrated Lcalac Rate Test - Post Operational 4 .4-1

• Local 1Pc'aetrati on Tosts 4 .4-I Recport oi* Tc:ýtz Results 4.4 -2 ISO) ati on Vl 4 .44- 3 ReSidual IknzRe:ova Systc'.1 4 .4-3 Tenclon ArC11nc End Arnc1oyopgc Concrete Surveillaince 4.4-6 liner Surv'CiM.Incc 4.4-7 4.5 sqýfty 7nT,-j-:ý,n 4I.5S-1 4.6 Elntrgonc~v Cr~rdn irmnnc~t Cool ingz Systemas 4. G-1 Er~'.gecy Cnti~:;c~~tFi) tcrin- and Plost Accidcnt 4.7 Contain;nc'nt Vecnt, Svstc:m^. 4.7-3.

4.8 E~evcmcvPc,,;er Systcrm Pcriodic Tests 4.8-1 4.9 1ai Stanlie atonValves 4.9-1 4.10 Auxi liar-)' cdz ( System' 4.10-1 4.11 Reactivity !xinc.:na) ics 4.11-1 4.12 Iwllirovn-antal R'adiation 'Survey 4.12-1 4.13 Radio,?ct.;vc M'.terlals Sources Surveillance 4.13-1 DESIGN' FElJFU]RES 5.1 Site 5.2 Reactor S.2-1 5.3 Con ta-iirucn t 5.'3-1 S.4 5.*4-1 6 AD.5IN'ISTR!',-f I%-,:- CO:;TrZOLs 6.1-1A 6.1 Responsibil ity 6-1 6.2 Organi zzztioný. 6-1 6.3 Facilitv S t-,f" Qualificat icns 6.4 6-5 Tra inin 6-S 6.5 Rcv~icw., and Audit 6.6 Reportable Occurrence Action 6-5 6.7 6-14 t25 Safety Lirý-.it \'iolaction.

6-14 6.8 Proceduros 6.9 6.14 Reporting Requirements 6-i ii.

1.14 , (Deleted) 25 1.15 POWER TILT The power tilt is the ratio of the maximum to average of the upper out-of-core normalized detector currents or the lower out-of-core mormalized detector currents whichever is greater.

If one out-of-core detector is out of service, the remaining three detectors are to be used to compute the average.

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than a minority--of the quorum shall have line `eesponsibility for operation of the facility.

6.5.2.7 REVII.Y The CNRB shall review:

a. The safety evaluations for 1) changes to procedures, equipment or systems and, 2) tests or experiments completed under the pro vision of Section 50.59, 10 CFR, to verify that such actic;s dia not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which in volve an unreviewed safety question as defined in Section 50.59, 10 CFR.

c. Proposed tests or experiments which involve an unreviewcd safety question as defined in Section 50.59, 10 CFR.

d. Proposed changes in Technical Specifications or Licenses.

e. Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal pro cedures or instructions having nuclear safety significance.

f. -Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety

g. All events which are required by regqlations or Technical 125 Specifications to be reported to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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• RE PCPORI,ABLE OCCUPTi'J-( AC'IIUN, 6.6.1 'The following actions shall be taken in the event of a REPORTABLE . 25

• OCCUJPXCE:

a. The REPORTABLE OCCUPRENCE shall be reported to the Commission 25 pursuant to the requirements of Section 6i9.

b. A Reportable Occurrence Report shall be prepared. The report 125 shall be reviewed by the Plant Nuclear Safety Coý=.ittee.

c. The Reportable Occurrence Report shall be submitted to the CNRB, 25 the Vice President of Power Resources, and the Conu,ission within the time allotted in Section 6.9, 6.7 SAFETY LIMIT VIOLkTION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The provisions of 10 CFR 50.36(c)(i)(i) shall be complied within

.immediately.

b. The Safety Linit violation shall be reported imnediately to the Commission, the Vice President of Power Resources and to the CNRB.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PINSC. This report shall describe

1) applicable circumstances preceding the violation, 2) effects of the violation upon facility components; systems or structures, and 3) corrective action taken to'prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the CNRB, the Vice President of Power Resources and the Commission within ten (10) days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section-5.1 and 5.3 of ANSI N18.7-1972 and Appendix "A" of USNRC Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 below.

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6.9 REPOPlTING REQUIREUfENTS In addition to ti*-_applicable reperting requirc --Ls of Title 10, Code of Federal Regulitions, the follow.,ing identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforcei:-ent unless otherwiise noted.

6.9.1. ROUTINE REPORTS

a. Startup Rpeort. A su:mary report of plant startup and pow:cr cscalation testing shall be submitted f'll'o-;*.n (1) receipt of an operating license, (2) am nd.ent to the license involving a pl-rnned increase in power level, or (3) installation of fuel that has a diffe.rent design and has been nanufactured by a different fuel supplier, the:

(4) modifications thn: may havG siclnificantly altercd plant.

nuclear, thermal, o- hydraulic performance of the of the tests identified in The report shall address each include a description of the the FSAR%and shall in general measured values of the op.rating conditions or character of istics obtained durirq'. the test program and a coip:.rison these values with design predictions and specifications.

Any corrective actiens that were required to obtain satisfactory operation shall also bc described. Any details required in license conditions additionnl specific this report.

based on other co-.mitrients shall be included in Startup reports shall be submitted within (1) 90 days (2) 90 foll6wing completion of the startup test program, of cor*.1crcial

.days following resimiption or commencement power operation, or (3) 9 months follorwing initial criti cality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of comner.cial power operation), supplc'entary reports shall be submitted at least every three months until all three events have been completed.

b, Annual OneratinQ P1enrortl/ Routine operating reports covering the operation of the unit during the previous calendar year should be submitted prior to March 1 of each year. The initial report shall be submitted prior to March I of the year following initial criticality.

The annual operating reports made by licensees shall provide a comprehensive summary of the operating experience gained during the year, even though some repetition of previously reported information may be involved. References in the annual op-efating report to previously submitted reports shall be clear.

1/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

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Each ar, !1 operating report shall inc? -e:

(1) A narrative summary of o,)er ating expericnce during the report period relating to safe operation of tnc I,,,clity, includlnr'- sa`fc, relatedc maintenance no- covered in itci I.b. (2)(e) below.

(2) For each outage.or forced reduction in pjowcr2/

of over 20% of design power ]evel where the reduction extends for greater than four hours:

(a) the proxir:atc c3use and the system and major component involved (if the outage or forced reduction in power involved equipment malfunction);

(b) a brief discu.csn of.(or refcrcnce to reports of) any reportable occurrences pertaining to the outage or power reduction; (c) corrective action taken to reduce the proba bility of recurrence, if appropriate; (d) operating time lost as a result of the outage or powNer reduction (for schc*cu]ed or forced outages,3/ use the generator off-line hours; for forcK'd reduction in po;..'er, use the approximate duration of operation at reduced power);

(e) a description of major safety-related corrective 25 maintenance performed during the outage or power reduction, including-n the system and cor.:ponent involved and identification of the critical path activity dictating the length of the outage or power reduction; and (f) a report of any single release of radioactivity or radiation exposure specifically associated with the.outage iwhich accounts for more than 10% of the allowable annual values.

2/ The term "forced reduction in power" 'is normally defined in the electric power industry as the occurrence of a component failure or other condition which requires that the load on the unit be reduced for corrective action immediately or up to and including the very next weekend.

Note that routine preventive maintenanc-e, surveillance and calibration activities requiring power reductions are not covered by this action.

_ The term "forced outage" is normally defined in the 61ectric power industry as the occurrence of a component failure or other condition

.which requires that the unit be removed from service for corrective action immediately or up to and including the very next weekend.

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(3) A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functions, 4- e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

(4) Indications of failed fuel resulting from irradiated fuel examinations, including eddy current tests, ultrasonic tests, or visual examinations completed during the report period.

c. Monthly Operating Report. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the appropriate Regional Office, to arrive no later than the tenth of each month following the calendar month covered by the report.

6.9.2 REPORTABLE OCCURRENCES Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC.

Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

4/ This tabulation supplements the requirements of 920.407 of 10 CFR Part 20 6-18

a. Prompt Noti. ation With W'ritten FollowUn. "e types of events listee below shall be reported as"exp-itiously as possible, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirpied by telegraph, mailgram, or facsimile transmission to the.

Director of the appropriate Regional Office, or his-designate no later than the first working day following the event, with a written followup report within two weeks. The written folloiup report shall include, as a minimum, a completed copy of a licensee event report form. Information providcd'on the licensee event report form shall be supple-ented,.

as needed, by additional narrative material to provide c.gm plete explanation of the circumstances surrounding the event.

(1) Failure of the reactor protection system or other -.

systems subject to limiting. safety system settings to initiate the required protective function by the time a monitored parameter ruaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.

Note: Instrument drift discover'ed as a result of testing need not be reported under this item but may be reportable under items.2.a(S), 2.a(6), or 2.b(l) " 25 below.

(2) Operation of the unit or affected systems when any- .

para-meter or operation subject to a limiting condition is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications*.

Note: If specified action is taken when a system, is found to be operating between the most conservative and the least conservative aspects of a limiting condition for operation listed in the technical specifications, the limiting condition for operation is not &onsidered to have been violated and need not be reported under this item, but it may be reportable under item 2.b(2) below.

(3) Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.

Note: Leakage of valve packing or gaskets within the limits for identified leakage set forth in technical spec ifications need not be reported under this item..

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(4) React_-..ity anomalies, involving disa<,ment with the predicted value of reFic ivtv 1aL,:nc- under .,-cýdy .*t;Ke conditions during i);.er op*.ration, greater than or equal to 1% Ak/k; a calculated rcactivit), balance indicating a shut down margin less conservative than specified in the technical specifications; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if sub-critical, an unplanned rcactivity insertion of more than 0.5% Ak/k or occurrence of any unplanned criticality.

(5) Failure or malfunction of ohe or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the SAR.

(6) Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirer.ients of systems required to cope with accidents analyzed in the SAR.

Note: For items 2.a(S) and 2.a(6) reduced redundancy that does not result -in a loss of system function need not be reportcd under this section but may be 25 reportable under items 2.b(2) and 2.b(3) below.

(7) Conditions arising from natural or man-made events that, as a direct result of the event r-quire plart shutdown, operation of safety systems, or other protective measures required by technical specifications.

(8) Errors discovered in the transient or accident analyses or in the ffiethods used for such analyses as described in the safety analysis report or in the bases for the technical specifications. tlhat have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

(9) Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a ranner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically con sidered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

6-20

Note: This em is intended to provide for - norting of potentially generic problems.

b. Thirty Day V'ritten Reports. The reportable occurrences discussed the Director below shall be the su',Jcot of written reports to of of thei appropri-ate Regional Office within thirty days occurrence of the event. The written report shall include, as report forim,.

a minimum, a conpleted copy of a licensee event event report form shall Information provided on the licensee additional narrative material be supplemented, as needed, by the circumstances surrounding to provide complete explanation of the event.

fclfatu (1) Reactor protection systerm or en-ineered a less conserv instrument settings which are found to be specifications ative than those established by the technical functional but which do not prevent the fulfillment of the requirements of affected systems.

mode (2) Conditions leading to operation in a degraded for operation or permitted by a limiting condition condition for plant shutdown required by a limiting operation. 25 Note: Routine surveillance testing, instrument calibration, or preventative maintenance which require system 2.b(2) configurations as described in items 2.b(l) and themselves need not be reported except where test results reveal a degraded mode as described above.

"'(3) Observed inadequacies in the implementation of admin to istrative or procedural controls which threaten provided in cause reduction of degree of redundancy safety feature reactor protection systems.or enginered systems.

(4) Abnormal degradation of systems other than those specified in item 2.a(3) above designed to contain radioactive material resulting from the fission process.

included Note: Sealed sources or calibration sources are not of valve packing or gaskets under this item. Leakage leakage set forth in within the limits' for identified technical specifications need not be reported under this item.

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6.9.3 SPECIAL REP 'S Special reports shall be submitted covering the activitie's identified below pursuant to the requirements of the applicable reference specification where appropriate.

Twenty copies of the following reports should be sent to the Director, Nuclear Reactor Regulation.

a. In-service inspection, reference'4.2.

b. Tendon surveillance, reference 4.4.

6.9.4 UNIQUE REPORTING REQUIREmeNTS

a. Radioactive Effluent Releases A report of the quantities of radioactive effluents released from the plant, with data summarized on a monthly basis following the format of U. S. NRC Regulatory Guide 21.

The report shall be submitted within 60 days after January I and 60 days after July 1 specifying qLuantities of radioactive effluents released during the pievious 6 months of operation.

1. Gaseous Releases (a) Total radioactivity (in curies) releases of noble and activation gases.

(b) Maximum noble gas release rate during any one-hour period.

(c) Total radioactivity (in curies) released, by nuclide, based on representative isotopic analyses performed.

(d) Percent of technical specification limit.

2. Iodine Releases (a) Total (1-131, 1-133, 1-135) radioactivity (in curies) released.

(b) Total radioactivIty (in curies) released, by nuclide, based on representative isotopic analyses performed.

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(c) ý'orcent of technical specificati*.'limit.

3. Particulate Releases (a) Gross radioactivity (*, y) released (in curies) excluding background radioactivity.

(b) Gross alpha radioactivity released (in curies) excluding background radioactivity.

(t) Total radioactivity released (in curies) of nuclides with half-lives greater than eight days.

(d) Percent of technical specification limit.

4. Liquid Releases (a) Gross radioactivity (0, y) released (in curies) excluding tritium and average concentration released to the unrestricted area.

(b) Total tritium and alpha radioactivity (in curies) released and average concentration released to the unrestricted area.

25 (c) Total dissolved gas radioactivity (in curies) and average concentration released to the unrestricted area.

(d) Total volume (in liters) of liquid waste released.

(e) Total volumie (in liters) of dilution water used prior to release from the restricted area.

(f) The maximum concentration of gross radioactivity (0, y) released to the unrestricted area (averaged over the period of release).

(g) Total radioactivity (in curies) released, by nuclide, based on representative isotopic analyses performed.

1) Percent of technical specification limit for total activity released.

5. Solid Waste (a) The total amount of solid waste packaged (in cubic feet) 6-23

(b) -,he total estimated radioactivi\ (in curies) involved.

(c) The dates of shipment and dfsposition (if shipped off-site).

b. Environmental Radiological Monitoring A report on the environmental monitoring program shall be submitted within 60 days after January 1 and 60 days after July 1 covering the previous 6 months of operation. This report may be combined with the report of the quantities of radioactive effluents.

1. For each medium sampled e.g., air, baybottom, surface water, soil, fish including:

(a) Number of sampling locations (b) Total number of samples (c) Number of locations at which levels are found to be significantly above local backgrounds (d) Highest, low'est, and the annual average concentrations or levels of radiation for the sampling point with the highest average and description of the location of that point with respect to the site.

2. If levels of radioactive materials in environmental media indicate the likelihood of public intakes in excess of 3% of those that could result from continuous exposure to the concentration values listed in Appendix B, Table II, Part 20, estimates of the likely resultant exposure to individuals and to population groups, and assumptions upon which estimates are based shall be provided.

3. If statistically significant variations of off-site environmental concentrations with time are observed, correlation of these results with effluent releases shall be provided.

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3/4 LEFT BLANK INTENITIONALLY 6-25 I

LEFT BLANK INTENTIONALLY 6-26

6.10 RECORD RETrV':TTOI 6.10.1 The following records shall be retnine'd for at least five (5) years:

a. Records and legs of facility operation covering time in:cr %,,l at each pcw'er level.

b. Records and logs of principal niintenance activities, j z, ticns, A

repair and replacement of pfinripil itehs of c-quiip,-.pnt r>l:c.

to nuclear safeLy>.

C. REPORTABLE OCCUl,:RNCE Reports.

25

d. Records of surveillance activitieu, inspection- and caiib-'rtions requirvd by these Technical Specifications.

e. Records of reactor tests and experirmnts.

f. Records of changes made to Operating Procedures.

g. Records of radioactive shipments.

h. Records of sealed source leak tests and results.

6-27

• -c

SAFETY EVALUATION BY THE OFFICE OF NUJCLEAR REtTOR REGULATION SULPPORTING AMENDIENT NO. 13 TO FACILITY LICENSE NO. DPR-31, AND AMENDMENT NO. 12 TO LICENSE NO. DPR-41 .

CHANGE NO. 25 TO TECHNICAL SPECIFICATIONS FLORIDA POKER AND LIGHT COMPAXY TURKEY POINT NUCLEAR GENERATING UNITS 3 AND 4 DOCKET NOS. 50-250 AND 50-251 Introduction By letter dated December 20, 1974, Florida Power and Light Company (FPL) proposed changes to the Technical Specifications appended to Facility Operating Licenses No. DPR-31 and DPR-41 for the Turkey Point Nuclear Generating Units 3 and 4. The proposed chanpes involve changes to the reporting requirements.

Discussion The proposed changes would be administrative in nature and would affect the conduct of operation. The proposed changes are intended to provide uniform license requirements. Areas covered by the proposed uniform specifications include reporting requirements and an abnormal occurrence definition change.

In Section 208 of the Energy Reorganization Act of 1974 "abnormal occurrences" is defined as an unscheduled incident or event which the Commission determines is significant from the standpoint of public health or safety. The term "abnormal occurrence" is reserved for usage by NRC. Regulatory Guide 1.16, "Reporting of Operating Information Appendix A Technical Specifications", Revision 4, enumerates required reports consistent with Section 208. The proposed change to required reports identifies the reports required of all licensees not already identified by the regulations and those unique to this facility. The proposal would formalize present reporting and would delete any reports no longer needed for assessment of safety related activities.

2 Evaluation The new guidance for reporting operating information does not identify any event as an "abnormal occurrence". The proposed reporting require ments also delete reporting of information no longer required and duplica tion of reported information. The standardization of required reports and desired format for the information will permit more rapid recognition of potential problems.

During our review of the proposed changes, we found that certain modifi cations to the proposal were necessary to have conformance with the desired regulatory position. These changes were discussed with your staff and have been incorporated into the proposal.

We have concluded that the proposal as modified improves the licensee's program for evaluating plant performance and the reporting of the operating information needed by the Commission to assess safety related activities and is acceptable. The modified reporting program is consi~stent with the guidance provided by Regulatory Guide 1.16, "Reporting of Operating Information - Appendix A Technical Specifications",

Revision 4. The administrative controls are consistent with requirements being incorporated in Technical Specifications for new licensed facilities.

Conclusion We have'-concluded, based on the considerations discussed above, that:

(1) because the change does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a.safety margin, 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.

Date: November 26, 1975

UNITF- STATES NUCLEAR REGULATORY COMMISSION DOCKETS NOS. 50-250 AND 5O-251 FLORIDA POWER AND LIGHT CO)*ANY NOTICE OF ISSUNINCE OF AMENDMENTS TO FACILITY OPERATING LICENSES Regulatory Commission Notice is hereby given that the U.S: Nuclear (the Commission) has issued Amendments Nos. 13 and 12 to Facility Operating Licenses Nos. DPR-31 and DPR-41 issued to Florida Power and for operation of the Light Company which revised Technical Specifications 3 and 4, located in Dade Turkey Point Nuclear Generating Units Nos.

County, Florida. Tle amendment is effective 60 days from the date of issuance.

of the The amendment modifies the reporting requirements Generating, Units Technical Specifications for the Turkey Point Nuclear 3 and 4.

standards and The application for the amendment complies with the as amended (the Act), and requirements of the Atomic Energy Act of 1954, the Commission's rules and regulations. The Commission has made the Commission's rules appropriate findings as required by the Act and forth in the license and regulations in 10 CFR Chapter I, which are set since amendment. Prior public notice of this amendment is not required consideration.

the amendment does not involve a significant hazards (1) the For further details with respect to this action, see 1974, (2) Amendments Nos.

application for amendment dated December 20, with Change No. 25 and (3) 13 and 12 to Licenses Nos. DPR-31 and DPR-41,

t

-2 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, D. C. and at the Environmental SUrban 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 Reactor Licensing.

-Dated at Bethesda, Maryland, this 26 day of November, 1975.

FOR THE NUCLEAR REGULATORY CO=IISSION Donald M4. Elliott, Acting Chief Operating Reactors Branch 43

• Division of Reactor Licensing