Regulatory Guide 1.16: Difference between revisions

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{{Adams
{{Adams
| number = ML12305A256
| number = ML13350A370
| issue date = 01/31/1975
| issue date = 10/31/1973
| title = Reporting of Operating Information - Appendix a Technical Specifications.
| title = Reporting of Operating Information
| author name =  
| author name =  
| author affiliation = NRC/RES
| author affiliation = US Atomic Energy Commission (AEC)
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.016, Rev 3
| document report number = RG-1.016, Rev. 1
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 13
| page count = 8
}}
}}
{{#Wiki_filter:Revision 3 January 1975 U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:-I                                                                                                                                      -                        Revision      1 Revision 1 October 1973 Se                                US. ATOMIC ENERGY COMMISSION
                                      REGULATORY
                                    REGULATORY
                                        DIRECTORATE OF REGULATORY                                 STANDARDS
                                    DIRECTORATE OF REGULATORY STANDARDS
                                                                                                                                      GUIDE
                                                                                                                                        GUIDE
                                                                        REGULATORY GUIDE 1.16 REPORTING OF OPERATING INFORMATION-APPENDIX A
                                                                      REGULATORY GUIDE 1.16 REPORTING OF OPERATING INFORMATION
                                                                  TECHNICAL SPECIFICATIONS


==A. INTRODUCTION==
==A. INTRODUCTION==
addressees and designation of the number of copies re- quired, is included in Regulatory Guide 10.1, "Compila- Section 50.36, "Technical Specifications," of 10                               tion of Reporting Requirements for Persons Subject t_0
the ('omliission's regulations is also included. The AEI'
        CFR Part 50, "Licensing of Production and Utilization                                 AEC Regulations," and is not presented-he-rein._
                                                                                              Regulatory staff has ieviewed Ihe types sf inorloratislat SCction 50.36. "TTechnical Specifications." of 10                               needed. Based oln !tis review and a review irf licensees'
        Facilities," requires that each applicant for a license authorizing operation of a nuclear power plant include in its application proposed technical specification
      CFR Part 50, "Licensing ot Production and Utilizationi                                 current reporting pt igrai.; the staff has developed Facilities," requires that easch applicant for a license                               guidelines fotr such repirtint.. Thik ituidc presents an authorizing operation of a nuclear power plant include                                 acceptable          reporting prourainn I ol powel reactor in his applica tion proposed technical specifications.                                licensees. Ta hles I and II o1 this guide are coilpilaliotm.s These technical specifications as approved by the AE-C                                of tinme limits or frequency :inlervals [tr subhnlitting are incorrporated into tire facility license and are                                    routline    and    nonroutline        report:,. Acceptable repoirtlin1 conditions oif the license. The technical specifications for                          programs tor radioactive eflluents and environnmen.tal nuclear power plants include a section on reporting                                    monitoring are presented in Regulatory Guides 1.21 requirements. In addition to the reporting requirements                                (Safety Gtmide 211. "Measuring and Reporting oft'
      necessary for compliance                          with the technical                  Effluents from Nuclear Pow\ver                                      and 4.1
                                                                                                                                                                  :lait<.
      specifications of the license, there are specific reporting                            "'Measuring and Reportine ofi' R:idioct'livilt                          itl the requirements included in Part 50 as well as in Parts 20.                                Environs of Nuclear Power P1lhnts."' respectively.


====s.     ====
40. 70. and 73 of Title 10. For the convenience of licensees, these specific reporting requirements are                                          Significant differences in Revision I of this guide included in the reporting program described in this                                    from Regulatory Guide 1.16o formerly Safety Guide 16)
      guide. Each report discussed in this guide is either                                  dated October 27, 1971 are:
      required by AEC regulations or is normally specified in licensees' technical specifications. In some cases this                                I. Extensive quoting of the Commission*, regulations program may need to be supplemented or modified                                        has been deleted. References to the appropriate portiots because of unique plant design features or other factors.                              of the Commission's regulations are included itt Tables I
      The need for a supplemental or modified program will                                  and !1 of this guide.
 
be determined on an individual-case basis. The Advisory Committee on Reactor S'feguards has heen consulted                                    2. For ease of reference the reporting summary table concerning this guide and has concurred in the                                        included in the original guide has been divided into two regulatory position.                                                                   tables (Routine Reports and Nonroutine Reports)


==B. DISCUSSION==
==B. DISCUSSION==
These technical specifications, as issued by the AEC, are incorporated into the facility license and are conditions                                    In September 1974 the Regulatory staff published of the license. Technical specifications are now included                              Revision 2 of Regulatory Guide 1.16. This revision re- as two appendices to the license: Appendix A technical                                flected results of a Regulatory staff review of operating specifications relate to health and safety, and Appendix                              intormation needed to permit assessment by the Com- B technical specifications relate to environmental im-                                mission of safety-related activities during the operating pact.' Each of these appendices includes a section on                                  phase of plant life. Significant differences in this guide reporting requirements. The reporting program' described                              from Revision 1 of Regulatory Guide 1.16, dated Octo- in this regulatorv guide involves the reporting require-                              ber 1973, were:
3. Reporting requirements have been updated ti reflect changes in the Comnmission's regulations and the reports required by the technical specifications.
        ments of Appendix A technical specifications only. In                                  1. Reporting requirements were updated to reflect
"Osome cases, this program may need to be supplemented                                        changes in reports required by Appendix A technical or modified because of unique plant design features or                                specifications. In general, these changes involved:
        other factors. The need for a supplemental or modified                                      a. a change in frequency of submittal of routine program will be determined on a case-by-case basis.                                    operating reports;
            0 Reporting of information concerning radioactive                                        b. elimination of the first-year operating report;
        discharges, radiological environmental monitoring, and                                     c.    formalization of reporting of operating infor- Q,-)  nonradiological environmental surveillance and environ-                                mation on a monthly frequency;
*    (  mental impact is discussed in Regulatory Guide 4.8,
        "Environmental Technical Specifications for Nuclear Power Plants."
                                                                                                    d. deletion of certain items of information no longer required by the AEC to be submitted on a routine basis;
                In addition to the reporting requirements necessary                                  e. changes in the format and immediacy of re- for compliance with technical specifications, specific                                porting required for certain types of abnormal occur- reporting requirements are included in Part 50, as well as                            rences; and in other Parts of Title 10, Chapter 1, Code of Federal                                      f. improved guidance concerning definitions and Regulations. A compilation of all reporting requirements                              categories of significance of abnormal occurrences.


applicable to the various types of AEC licensees, in-                                 2. Appendices B, C, D, and E were added to provide cluding identification of the proper AEC addressee or                                the desired format for radiation exposure reports and monthly operating reports.
The information provided in the reports discussed herein should be sufficient to permit an assessment by the Commission of all safety-related activities during and                            4. Appendix A of this guide. "Standard iormtatl I't following the startup of the facility.                                                 Reporting Abnorinal Occuirrences." ha,: h'etn added to give guidance to licensees suhmittinzg abnormal occurrence reports.


3. A listing of reports other than those required by
In addition to those reports that relate to the safety of operation of the plant, the information on nuclear                                "Lines indicatc substantive chaivs O'wn10plcvihitls isslie.
                'A few facilities have a single appendix that contains the                   Appendix A technical specifications was eliminated. (See combined aspect of Appendices A and B.                                                Introduction above.)
                                USAEC REGULATORY GUIDES                                      Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public          Attention: Director of Regulatory Standards. Comments and suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of    improvements in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques .red by the staff in        of the Commission, U.S. Atomic Energy Commission, Washington, D.C. 20545, evaluating specific problems or postulated accidents, or to provide guidance to    Attention: Docketing and Service Section.


applicants. Regulatory Guides are not substitutes for regulations and compliance with them is not required. Methods and solutions different from those set out in    The guides are issued in the following ten broad divisions:
materials safeguards that must be reported pursuant to USAEC REGULATORY GUIDES                                        Copies of published guides may be obtained by routs' ,ldicanig the divisions desired to the US. Atomic Energy Commission. Washinglon. D.C. 20545.
          the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.                 1. Power Reactors                         


===6. Products===
pleguletory Guides are sisued to describe and make avrtable to the public            Attention: Director of Regulatory Standards. Comments and wu9grtiodls tfo methods acceptable to thP AEC Regulatory stalf ot Implementing &peailicparis of      ImprOvements In these guides ere encourAged and shotrid be ient to the Secretary the Comtn4tion's regulations. to delineate technijuest used by the Staff in          of the Commission, U.S. Atomic Energy Commission. W*%hinl.to. D.C. 20545.
                                                                                                2. Research and Test Reactors             


===7. Transportation===
evaluating specific problems or potiulated accidents, or to provide guidance to     Attention: Chief. Public Proceedings Stafl.
                                                                                                3. Fuels and Materials Facilities          8. Occupational Health Published guides will be revised periodically, as appropriate, to accommodate        4. Environmental and Siting                9. Antitrust Review comments and to reflect new information or experience.                               5. Materials and Plant Protection        1


===0. General===
ipplicants. Regulatory Guides are not substitutes for regulations and compliance with them ihnot required. Methods and eolutions different from those set oul In      I he guides are issued in the following ten broad dcviSons:
      the guides will be acceptable If they provide a basit for the findings requisi            Power Reor
                                                                                            2. RePearch and Test Reactors             


6 Comments were invited within 60 days of publica-                scribed. Additional specific details may be included in tion of Revision 2 for use in conjunction with early                  license conditions based on the applicant's commitment revision of the guide. As a result of~comments received              to applicable Regulatory guides and should be included          -
===7. Products===
on the guide and additional staff review, the Regulatory              in this report.
                                                                                                                                        6. T      samotatne the issuance or continuance of a permit or license by the Commission.


staff has developed Revision 3 to Regulatory Guide                              Startup reports should be submitted within (1)
3. Fuels ant] Materials Facilities         
1.16.                                                                90 days following completion of the startup test Significant differences in this guide from Revision 2          program, (2) 90 days following resumption or com- of Regulatory Guide 1.16, dated September 1974, are:                mencement of commercial power operation, or (3) 9
1. The startup report was revised to be more specific as            months following initial criticality, whichever is earliest.


to the test results to be reported.                                 If the Startup Report does not cover all three events
===8. Occuttationiri Hal h===
2. The annual report section was revised to (1) further              (i.e., initial criticality, completion of startup test pro- quantify the term "reduction in power," (2) provide                  gram, and resumption or commencement of commercial further guidance on reporting of occupational radiation              power operation), supplementary reports should be sub- exposures, and (3) revise the information to be sub-                  mitted at least every three months until all three events mitted on fuel performance.                                          have been completed.
                                                                                            4, Envitonmntol and Siting                  9. Ar-rtruit Rr.v,ewv Published guides will be revised periodically, as a~ptopriate, to accommodalte        5. Materialsand Plant Protection          10. Genetal commentS and to reflect new information or eaperience.


3. The abnormal occurrence report section was revised to (1) provide for prompt notification by telephone and confirmation of such notification by telegraph, mail-                      b.    Annual Operating Report.', 23 gram, or facsimile transmission of the types of abnormal occurrences listed under Section 2.a, (2) be more                                Routine operating reports covering the opera- specific on the types of abnormal occurrences reported,              tion of the unit during the previous calendar year should
,, ,III                                  I*1]11 II                            *    III- - - -
(3) delete radiological effluent releases from Appendix A            be submitted prior to March 1 of each year. The initial technical specification reporting requirements, (4) pro-             report should be submitted prior to March 1 of the year vide for reporting of the types of abnormal occurrences              following initial criticality.
 
listed under Section 2.b within 30 days of occurrence of                          The primary purpose of annual operating the event, and (5) make Section 2.c of Revision 2 of the              reports is to permit annual evaluation by the AEC staff guide a separate section (Section 4).                                of operating and maintenance experience throughout the nuclear power industry. The annual operating reports made by licensees should provide a comprehensive sum-  


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
mary of the operating experience gained during the year,l even though some repetition of previously reporte In addition to the applicable reporting requirements            information may be involved. References in the annual of Title 10, Code of Federal Regulations, the following              operating report to previously submitted reports should program for reporting of operating information provides              be clear.
(d) a progress and status report oir airy items    identified as requiring additional inforitation The following reporting program should be used to                                             during    tire operating license review or during the startup implement the reportintg requirements of 10 CFR Parts                                                of tlie    facility, including ilemns discussed in tile AEC's
 
20, 40. 50. 70. 73, and teporting requirenments imposed                                              Safely      Evaluation Repmrt and Supplements, items on by the AEC as license conditions. including those reports                                            which      additional information was required as a required by thie tclnlical specilrCations.                                                           conrdition of the license. and itemrs identified in the licensee's st:artup report: and
an acceptable basis to the Regulatory staff for meeting                          Each annual operating report should include:
1.     Routine Reports                                                                                                (e) a report of measured in-plant radiation levels which are greater thiran those estimated irr the final a.        Operations Reports'                                                                safety analysis report by a factor of two or more.
the reporting requirements of Appendix A technical                                (1) A narrative summary of operating expe- specifications. Reports submitted in accordance with                  rience during the report period relating to safe operation this guide should be addressed to the Director of the                of the facility, including safety-related maintenance not appropriate Regulatory Operations Regional Office                    covered in item 1.b.(2)(e) below.
 
unless otherwise noted.                                                          (2) For each outage or forced reduction in power 4 of over 20 percent of design power level where
1. Routine Reports                                                  the reduction extends for greater than four hours:
                                                                                      (a) the proximate cause and the system a.   Startup Report.                                           and major component involved (if the outage or forced reduction in power involved equipment malfunction);
          A summary report of plant startup and power escalation testing should be submitted following (1)
receipt of an operating license, (2) amendment to the
                                                                            2 license involving a planned increase in power level, (3)                      A single submittal may be made for a multiple unit installation of fuel that has a different design or has been        station. The submittal should combine those sections that are manufactured by a different fuel supplier, and (4)                  common to all units at the station.
 
modifications that may have significantly altered the                        S'Much of the information in the Annual Report was nuclear, thermal, or hydraulic performance of the plant.            previously submitted in a Semiannual Report.
 
4 The term "forced reduction in power" as ued in this guide The report should address each of the tests identified in and as normally defined in the electric power industry means the the FSAR and should in general include a description of              occurrence of a component failure or other condition which the measured values of the operating conditions or                  requires that the load on the unit be reduced for corrective characteristics obtained during the test program and a              action immediately or up to and including the very next week- comparison of these values with design predictions and              end. .Note that routine preventive maintenance, surveillance, and specifications. Any corrective actions that were required            calibration activities requiring power reductions are not covered to obtain satisfactory operation should also be de-                  by this section.
 
1..16-2
 
(b) a brief discussion of (or reference to            Office, to arrive no later than the tenth of each month
*reports        of) any abnormal occurrences pertaining to the              following the calendar month covered by the report.
 
Ioutage or power reduction;
                        (c) corrective action taken to reduce the            2.  Abnormal Occurrences probability of recurrence, if appropriate;
                        (d) operating time lost as a result of the                Licensees are required to investigate and evaluate outage or power reduction (for scheduled or forced                    the significance of abnormal occurrences and implement outages,s use the generator off-line hours; for forced                corrective actions to prevent recurrence, in accordance reductions in power, use the approximate duration of                  with provisions of technical specifications and the pro- operation at reduced power);                                          gram for quality assurance during the operational phase (e) a description of major safety-related            of plant life. In addition, abnormal occurrences, in- corrective maintenance performed during the outage or                  cluding corrective actions and measures to prevent reoc- power reduction, including the system and component                    currence, should be reported to the AEC as described involved and identification of the critical path activity              below.
 
dictating the length of the outage or power reduction;                            In general, the importance of an occurrence and                                                                    with respect to safety significance determines the (f) a report of any single release of radio-          immediacy of reporting required. In some cases, how- activity or radiation exposure specifically associated                ever, the significance of an event may not be obvious at with the outrage which accounts for more than 10 per-                  the time of its occurrence. In such cases, the AEC should cent of the allowable annual values.                                    be informed promptly of an increased significance in the
                  (3) A tabulation on an annual basis of the                licensee's assessment of the event. In addition, supple- number of station, utility, and other personnel (in-                  mental reports may be required to fully describe final cluding contractors) receiving exposu'res greater than                  resolution of occurrence. In some cases of corrected or
       100 mrem/yr and their associated man-rem exposure                      supplemental reports, a licensee event report should be according to work and job functions, 6 e.g., reactor                    completed and reference should be made to the original operations and surveillance, inservice inspection, routine              report date. Guidance concerning reportable occurrences maintenance, special maintenance (describe mainte-                      that should be reported in different time frames is pro- nance), waste processing, and refueling. The dose assign-              vided below.
 
ments to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge.measurements.                        a.    Prompt Notification With Written Followup.


*,iSmall exposures totalling less than 20 percent of the individual total dose need not be accounted for. In the                            The types of events listed below should be aggregate, at least 80 percent of the total whole body                  reported as expeditiously as possible, but within 24 dose received from external sources should be assigned                  hours by telephone and confirmed by telegraph, mail- to specific major work functions. See Appendix B to this                gram, or facsimile transmission to the Director of the guide for a standard format for providing this infor-                   appropriate Regulatory Operations Regional Office, or mation.                                                                 his designate, no later than the first working day fol-
I I ) Startup Report. A summary. report of plant                                                (3) Semiannual Operating Reports? Routine startot) and power escalation testing should he submittcd                                          operating reports covering tire operation o tIrh pre2 hus I'o0lowitrg reccipi t it' ai upctatintg license, tollowing an                                      (I mionths should be subtrmitted witiirt 60 days after amendment it the licenise involving -a planned increase in                                          Jartnuary I and Jtly I of each year. The initial report power level. ft,..owin            iv the iLnstall.'tinn of rrel il has if                          shtitld he stthlirited Withint 00 days after the cild iI' the different design ur hlas been nranuutfactrrred by a different                                      first six-nmonth period during which initial criricalily fuel supplier. or fIOllowing modi fications dial nay haive                                          took place. Fa ch report should inelnrde the followirrg:
                  (4) Indications of failed fuel resulting from              lowing the event, with a written followup report within irradiated fuel examinations, including eddy current                  two weeks. The written followup report should include, tests, ultrasonic tests, or visual examinations completed              as a minimum, a completed copy of the licensee event during the report period.                                             report form (see Appendix A to this guide) used for entering data into the AEC's computer-based file of in- c.    Monthly Operating Report.                                  formation concerning licensee events. (Instructions for completing these license event report forms7 are issued Routine reports of operating statistics and shut-          individually to each licensee.) Information provided on down experience should be submitted on a monthly                      the licensee event report form should be supplemented, basis. The report formats set forth in Appendices C, D,                as needed, by additional narrative material to provide and E to this guide should be completed in accordance                  complete explanation of the circumstances surrounding with the instructions provided. The completed forms                    the event.
signifilcantly ahlrred the nuclear. thermal. or hydranlic perftorniance iI"Ithe pl:ant. The report should include a                                                             (a) Operations Sumrnmar'. A stinrirary of description of The :mc:c*scIcd ';iltiues tit' the ocerating                                          operating experience occurring during the reportiog conditions or ctharacteristics obtained during the test                                              period that relates to tire s:icuoperation of the facility.


should be sent to the Director of Regulatory Operations,                          (1) Failure of the reactor protection system or U.S. Atomic Energy Commission, Washington, D.C.                        other systems subject to limiting safety-system settings
progratn and a comnparison of these values with design                                              including a sumnmary of:
      20545, with a copy to the appropriate RO Regional                      to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety-system setting in the technical specifi- sThe term "'forced outage" as used in this guide and as cations or failure to complete the required Protective normally defined in the electric power industry means the occur- rence of a component failure or other condition which requires
predictions and specifications. Any corrective actions                                                                        (i) changes in facility design.
*      that the unit be removed from service for corrective action
      .immediately or up to and including the very next weekend.


6 This tabulation supplements the requirements of &sect; 20.407            'Instruction Manual, Licensee Event Report File, Office of of 10 CFR Part 20.                                                     Operations Evaluation, USAEC, Washington. D.C. 20545.
that Were requ.ired to obtain sattisfactlotv operarior                                                                        (it) performance characteristics (e.g..
should also he' dcr itwcd. Sr rtrup reporls sluimld lie                                              eqttipreti t ;tnid fuel per formlance),
slrblnlilrled willitm I1) 10 clays following cormpletion of                                                                   (iii) changes in) operating procedutres Ire stalt tip test ptoigra in. (2) 90 days following                                                which were necessitated by (i) and (ii) above or which resturnpli crrit ior c                    ntten nt o1f c rommerciaI po'wer                          otherwise were required to improve thie saklty of operation. or 31 t ) nronths following initial criticality.                                          operations, whichever is earliest. If thie Startutp Report does not                                                                      (iv) results of surveillance tests and cover all tihrec cverrts. i.. initiial criticalily. cotmlpletion                                    inspections required by the licensee's technical ot      S :crl tip t Cst plro ra iii. rod resl rillpt loll or                                      speciftications.


1.16-3
ce tonmterncete.                  *of      :o    Inetrrc ial  poe'r        operatiion.                                      (v) the results of aniy periodic Suplplementa'ry rep.crts Slhou.ld he srtbitritted at least                                          cottainment leak rate tests performed during the every lthrce rir*ithl trit ;i ll! hi c evonts are t.orrpleted.                                      reporting period.


function. The following are examples:                              $1.00; a calculated reactivity balance indicating a shut- (a) Reactor pressure exceeds limiting                down margin less conservative than specified in the tech- safety-system setting value without automatic trip.                nical specifications; short-erm reactivity increases that (b) Inability to trip and insert sufficient          correspond to a reactor period of less than 5 seconds or, control rods to achieve the technical specification shut-          if sub-critical, an unplanned reactivity insertion of more down margin.                                                        than 50N; or occurrence of any unplanned criticality.
(vi) a brief suimmary of tirosk cihtanges.


(c) Failure of the reactor protective sys-                    (5) Failure or malfunction of one or more tem to complete the required protective action once                components which prevents or could prevent, by itself, initiated.                                                         the fulfillment of the functional requirements of sys- tem(s) used to cope with accidents analyzed in the SAR.
(2) First Year Operaton Report. A report                                            tests. and experiments requiring auLthorization from the sh1trld hC subnrittled wit hin 60 days aftier completion of                                         Commission purtntant to 10 CMR 50.59(a), and the first year oit operalion. This .tar begims oc                                                                              (vii) any chanrges in thie p1lnt operating coltplet ion tt'oall three evetlt s listed in C.;.a.i i ). This                                      staff for thiose positions designated as key stipervisory report mtay he incorpor:ated into tile semiatrtrtl                                                  personniel positions in the technical specificairs.


Note: Instrument drift discovered as a result of testing            The following are examples:
olperatrino relport rard shurld cover tire following:
need not be reported under this item but may be report-                            (a) Clogged fuel line(s) resulting in failure able under items 2.a(5), 2.a(6), or 2.b(l) below.                   to supply fuel to the emergency generators.
                      (:ill ;m ,nv:ltr;!tit1In '; plhrtl p*rltl'lrr ltcc hi                                            (b) Power Generation. A sumnnmary of dale in corinlprisim wi! Ii 'sicti                                  !tiedicticlns and                powet generated during the reporting period including:
    S1ilic.l    jihltilsl'*        O:              iI                      ,ilil  .**                                    (iM gross thermal power geterated (itn MWI 1).
subriitied Witlh the license application i1" measured                                                                          (ii) gross electrical power generated operating characteristics indicate that there may be                                                                                (in MWH),
substantiialvariance fronm prior analyses:2                                                                                   (iii) number of iours tire reactor was (c) an assessrenrt of file performance of                                                                    critica!,
strtctures. sysletrs. and components iml'-rtant to                                                                             (iv) number of hours the generator safety:                                                                                                                              was on line, and (v) histogram of thermal power vs.


(b) Multiple instrument drift resulting in
iti, Ca, thill    L l.!,. .1titihctcld  bheS.tllrith: ill writirg tI0                                            t if e.
          (2) Operation of the unit or affected systems            loss of protective function.


when any, parameter or operation subject to a limiting                              (c) HPCI failure to start or failure to con- condition for operation is less conservative than the least        tinue running once initiated.
Ie    I)reclror orI rth e ;Ipprlrltialte AViC Re utailort - (i,,cration                  n Regionial Office.


conservative aspect of the limiting condition for opera-                      (6) Personnel error or procedural inadequacy tion established in the technical specifications. The               which prevents or could prevent, by itself, the fulfill- following are examples:                                            ment of the functional requirements of systems required (a) Shutdown not begun within the speci-            to cope with accidents analyzed in the SAR. The fol- fied time when unidentified reactor coolant leakage                lowing are examples:
'A sinrde subliimr itl may be imadrde    for a multiple facility
exceeds the technical specifications limit.                                         (a) Failure to restore a safety system to (b) Failure of a system other than the              operability following test or maintenance.
      2I'rciously  r        it rit    tedl    sal    % ;! raysi.s    repo r    r    i  V.          mat iim. The stticrrthittal shiould corritine tinrow. eclions Irh are inLccrloritlcl hb t eretilrce.                                                                       comllrrrlrn iI all I'acilitics at ilre station.


systems subject to limiting safety-system settings (see                            (b) Improper procedures leading to incor-
I .I0c-2
2.a(1) above) to actuate, or actuation of such a system            rect valve lineup which resulted in closure of one manual at a monitored parameter value less conservative than              valve in each of two redundant safety injection sub- that listed in the technical specifications for the system.        systems and would have prevented injection on demand.


(c) Operation with unacceptable contain- ment leak rate type B or C test results.                           Note: For items 2.a(5) and 2.a(6) reduced redundancy (d) System cooldown at a rate exceeding              that does not result in loss of system function need not the technical specifications limit.                                 be reported under this section but may be reportable under items 2.b(2) and 2.b(3) below.
I *
                    (c) Shutdowns. Descriptive material                                  (g) Occupational        Personnel  Radiation covering all outages occurring during the reporting                                        Exposure period. For each outage, information should be provided oil:                                                                                       i) A tabulation of 0i1e titinher Of (i) tile cause of the outage,                    occupational personnel exposures for plan' operations (ii) the inethud of shutting down the            personnel (permanent and temporary) in the following
    ]reactor; e.g.. trip, automatic rundown, or manually                  exposure increments for the reporting period: less thatn controlled deliberate shutdown'                                      100 mrerm, 100-250 ortem. 250-500 ntoem. 5001-750
                          (iii) duration of the outage (in hours),        morem, 750-1000 mrem. 1-2 rem. 2.3 retn. 3.4 rem. 4-S
                          (iv) plant status during the outage'            rem, 5.6 rem, and greater than 6 remi.


Note: If specified action is taken when a system is found to be operating between the most conservative                          (7) Conditions arising from natural or man- and the least conservative aspects of a limiting condition          made events that, as a direct result of the event, require for operation listed in the technical specifications, the          plant shutdown, operation of safety systems, or other limiting condition for operation is not considered to              protective measures required by technical specifications.
e.g.. cold shutdown or hot standby, and (v) corrective action taken to prevent                                (ii) A tabulation of the nurniter ot'
    repetition, if appropriate.                                          personnel receiving more than 500 mrem exposure in the reporting period according to duty function le.g..
                      (d) Maintenance. A discussion of                    routine plant surveillance and inspection (regular duty),
    corrective maintenance (excluding preventive                          routine plant maintenance, special plant mainten:itce maintenance) performed during the reporting period on                (describe maintenance). routine fueling operation.


have been violated and need not be reported under this              The following are examples:
safety-related systems and components4 and on systems                special refueling (,peration (describe opetation*. and and components that reduce or prevent the release of                  other job-related exposures.]
item, but it may be reportable under item 2.b(2) below.                            (a) Threatened civil disturbances requiring plant shutdown.
    radioactive materials to the environs. For any malfunction for which corrective maintenance was                                          (iii) A tabulation annually of the required, information should be provided on:                         number of personnel receiving more than 3 rein atnd fie (i) t he system or component                    major cause(s).
                                involved, (ii) the cause of the malfunction.                              (hi) FSAR Changes. Submission of revised (iii) the results and effect on saf.            FSAR pages on a replacement page basis appropriately operation. and                             r7epared for direct insertion into the applicable FSAIR
                          (iv) corrective action taken to prevent          section and describing all safety.related chaniges in'
                                repetition.                                facility design. method of operation. revised safety or transient analysis. or f:,cility equipment additiots. Also a (e) Changes, Tests and Experiments. A                listing of effective pages by date of revision or revisiotn brief description and the summary of the safety                        number should be submitted.


(3) Abnormal degradation discovered in fuel                              (b) Damage to the facility caused by fire, cladding, reactor coolant pressure boundary, or primary            flood, earthquake, or other similar occurrences.
evaluation for those changes, tests, and experiments, carried out without prior Commission approval pursuant                      b. Additional Routine Reporting Requirements.


containment. The following are examples:                                      (8) Errors discovered in the transient or acci- (a) Through-wall failure of piping or com-          dent analyses or in the methods used for such analyses as ponents of the reactor coolant pressure boundary.                   described in the safety analysis report or in the bases for (b) Steam generator tube thinning in                the technical specifications that have or could have per- excess of acceptance limits in Regulatory Guide 1.83,               mitted reactor operation in a manner less conservative
to the provisions of IOCFR 50.59(b).                                  Table 1 lists routine reports required by 10 CFR Parts
"Inservice Inspection of Pressurized Water Reactor                  than assumed in the analyses. The following are exam- Steam Generator Tubes."                                            pies:
                                                                            20. 40, 50. and 70. including those listed in Regulatory (f) Primary Coolant Chemistry. A                      Position C.I .a.
              (c) Welding or material defects greater                              (a) Loss of condenser vacuum resulting in than those allowable by applicable codes.                          reactor pressure and flux transients that peak at values higher than analyzed.


Note: Leakage of valve packing or gaskets within the                               (b) Reactivity insertion delay times by re- limits for identified leakage set forth in technical specifi-      actor protection system longer than those used in the cations need not be reported under this item.                      technical specification bases.
tabulation on a monthly basis of the maximum. average, and minimum values for the following primary coolant system parameters:                                                  2.    Nonroutine Reports (i) Gross radioactivity in pCi/ml.


(9) Performance of structures, systems, or
(ii) Suspended solids in parts per                    a.  Reporting of Abnormal Events
          (4) Reactivity anomalies involving disagree-            components that requires remedial action or corrective ment with the predicted value of reactivity balance                measures to prevent operation in a manner less conserva- under steady state conditions greater than or equal to              tive than that assumed in the accident analyses in the
                                                                                      (1) Abnormal Occurrence Reports. A
                                                            1.16-4
                                million.


safety analysis report or technical specifications bases; or      graded mode permitted by a limiting condition for discovery during plant life of conditions not specifically        operation, or plant shutdown required by a limiting considered in the safety analysis report, or technical            condition for operation. The following are examples:
notification must be made within 24 hours by telephone (iii) Gross tritium in pCi/ml.
*  specifications that require remedial action or corrective                        (a) Core spray pump breaker tripped after measures to prevent the existence or development of an            20 minutes during test. Trip unit was found to be defec- unsafe condition. The following are examples:                      tive, declared inoperable, and repaired.


(a) Axial flux ratios less conservative than                       (b) Safety injection pump failed to start those for which correlations with overpower AT were                following system initiation. Required surveillance on based on core burnup projections.                                 redundant components was successfully completed.
(iv) Iodine 131 in pCi/ml,                       and telegraph to the Director of the appropriate AlFC
                          (v) Ratio of Iodine-131                to       Regulatory Operations Regional Office. (cc to the Iodine-I133.                               Director of Licensing) followed by a written report wihrin 10 days to the Director of the appropriate AlEC
                          (vi) Hydrogen in cc per kg.


(b) Failure of a safety injection pumpto                          (c) One of the two centrifugal charging deliver the flow rates assumed in the FSAR.                       pumps became inoperable because of a faulty bearing.
(vii) Lithium in parts per million.              Regulatory Operations Regional Office in the event of (viii) Boron-lO in parts per million.           an abnormal occurrence.


(c) Degradation of hydraulic shock sup-             Redundant pump operability, was confirmed.
(ix) Oxygen-16 in parts per billion, Appendix A of this guide, "Standaid (x) Chloride in parts per million, and Format for Reporting Abnormal Occurrences.- should (xi) pH at 250 C.


pressors to the extent that they could not perform their required safety function.                                          Note: Routine surveillance testing, instrument calibra- (d) Failure of magnetic trip mechanisms            tion, or preventive maintenace which require system on a safety-related circuit breaker to provide trip on            configurations as described in items 2.b(l) and 2.b(2)
be used as guidance when submitting abnotmtal occurrence reports.
  instantaneous overcurrent as indicated on the manufac-            need not be reported except where test results theni- turer's time-current characteristic curve.                        selves reveal a degraded mode as described above.


(e) Failure of a safety/relief valve to close after pressure has reduced below the required reseat                         (3) Observed inadequacies in the implementa- valve.,                                                            tion of administrative or procedural controls which (f) Thermal shock to the reactor coolant            threaten to cause reduction of degree of redundancy system resulting from inadvertent safety injection actua-          provided in reactor* protection systems or engineered tion.                                                             safety feature systems. The following are examples:
4Those plant features necessary to assure the integrity of the reactor coolant pressure boundary. the capability to shut                         Abnormal occurrences are defined in the down the reactor and maintain it in a jal'vo shtdown condition.       definitions section of the licensee's technical consequences of1 or the capability to prevent or miti~oc tite                          specifications and usually include, as a miniutitll, items accidents which could result in o''.itc e,'i.sures comparable to the guideline exposures of 10 CFR Part 100.                           (a) through (h) of this paragraph.
                                                                                    (a) One of the three diesel generators Note: This item is intended to provide for reporting of tripped from high temperature because cooling water potentially generic problems.                                      valves were lined up incorrectly.


(b) Isolation valve for a low-pressure trip b.  Thirty-Day Written Reports.                              switch was found closed with system pressure locked in.
1 1 -3


Trip of switch would not occur at low pressure. Im- The abnormal occurrences discussed below have            proper return to operation following maintenance was
(a)  A  safety.  systeil    setting-  :ess                  (2) Reporting of Unusual Events. A written conlservative titan the limiting setting, established in the        report should be forwarded within 30 days to the technical specifications.                                          Director of t(ie appropriate AEC Regulatory Operations (b) Conditions which result in a limiting            Regional Office, in the event of:
*  lesser immediate importance than those described under            the cause.
condition for operations established in the technical                              (a) Discovery of any substantial errors in specilfications not being met.                                     the transient or accident analyses, or in the methods
                '0 Abnormal degradation of one of thie              used for such aitalyses. as described in the Safety several boundaries designed to contain radioactive                  Analysis Report or in the bases for the technical materials.                                                          specificat ions.


'2.a above. Such events should be the subject of written                           (c) Failure to perform surveillance tests at reports to the Director of the appropriate Regulatory              the required frequency.
(d) An unplanned or uncontiolled release                           (b) Discovery of any substantial variance of radioactive material from the site boundary.                    from performance specifications contained in the (e) Uncontrolled or unanticipated changes            technical specifications or in thle Safety Analysis Report.


Operations Regional Office within 30 days of occurrence                      (4) Abnormal degradation of systems other of the event. The written report should include, as a             than those specified in item 2.a(3) above designed to minimum, a completed copy of the licensee event report            contain radioactive material resulting from the fission form (see Appendix A to this guide) used for entering              process. For example, a through-wall leak in a liquid data into the AEC's computer-based file of information            waste storage tank.
in reactivity "qual to or greater than 1%Akikk.                                    (c) Discovery of any condition involving a
                (') Incidents or conditions which                  ipossible single failure which. for a system intended to be prevented or could have prevented the performance of                designed against assumed single failures. could result in a thle intended safely function of an engineered safely              loss of the capability Of the system to perform its safety feature system or of the reactor protection system.                 'loun ion.


concerning licensee events. (Instructions for completing these licensee event report forms 7 are issued individually        Note: Sealed sources or calibration sources are not in- to each licensee.) lnformation'provided on the licensee            cluded under this item. Leakage of valve packing or event report form should be supplemented, as needed,              gaskets within the limits for identified leakage set forth by additional narrative material to provide complete              in technical specifications need not be reported under explanation of the circumstances surrounding the event.            this item.
(g) Observed inadequacies            in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause                      b.  Additional        Nonroutine        Reporting the existence or development of an unsafe condition in                         Requirements connection with tile opelation of the plant.


(1) Reactor protection system or engineered safety feature instrument settings which are found to be          3.  Unique Reporting Requirements less conservative than those established by the technical specifications but which do not prevent the fulfillment                The above reporting program will in general satisfy of the functional requirements of affected systems. The            the reporting requirements necessary for compliance following are examples:                                            with Appendix A technical specifications. This program (a) One of the four scram dump volume              may need to be supplemented or modified because of level switches failed to operate during surveillance test..       unique plant design features or other factors. The need (b) One of four reactor low-pressure                for a supplemental or modified program will be deter- switches operated at 885 psig instead of LSSS value of            mined on a case-by-case basis and so designated in in-
(h) Conditions arising from natural of                          Table II lists nonroutine reports required by 10
  900 psig.                                                          dividual operating licenses.
man-made events that affect or threaten to affect the               CFR Parts 20. 40, 50, 70, and 73. including those listed sale operation of the plant.                                       in Regulatory Position C.2.a.


(c) During test, one out of four under- voltage relays failed to perform its function of tripping a        4.  Events of Potential Public Interest reactor trip breaker.
5A~defined in 10CF]R 50.36(c).
                                                                                                                                i
                                                              1.16-4


(2) Conditions leading to operation in a de-                  The types of events listed below are frequently of
0e                                                        TA8LE I
                                                                1.16-5
                                    REPORTING SUMMARY-ROUTINE REPORTS*
    Requirement                      Report                                        Timing of Submittal T'SI            Startup                                    Within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3)
                                                                9 months following initial criticality. whiiclhever is earhest.


high public interest. While some of the events may not       if the time for repair is likely to exceed the time allowed be reportable by regulation or defined in other parts of      by the technical specifications.
If all thrce events arc not completed. supplementairy reports every 3 monu~ths.


this guide, the Director of the appropriate Regional Office, or his designate, should be informed of such                           
TS                First Year ()perat.on                      Within 60 days after completion of the first yeat of operation.


==D. IMPLEMENTATION==
TS                Semiannual                                  Within 60 days after January Iand July I of each year.
events by telephone as soon as possible after the event has been discovered.                                                The purpose of this section'is to provide informa- tion to applicants and licensees regarding the Regulatory a. An event that causes damage to property or            staff's plans for utilizing this regulatory guide.


equipment when such damage affects the power produc-                Except in those cases in which the applicant pro- tion capability of the facility.                             poses an acceptable alternative method, the reporting b. Radiation exposure to licensee personnel or           program described herein is being used by the Regula- members of the public in excess of applicable exposure        tory staff in order to standardize the reporting require- limits set forth in 10 CFR Part 20.                          ments section of Appendix A technical specifications of c. Natural or man-made conditions that may re-          all operating licenses.
&sect;20.407          Personnel Exposure and Monitoring           Within first quarter of each calendar year.


quire action which need not be reported under item -                For licensees holding operating licenses without
&sect;20.408          Personnel Exposure on Termination of       Within 30 days after the exposure of the individual has Employmenit or Work                        been determined or 90 days after date of termination of employment or work assignment. whichever is earlier.
2.a(7) above.                                                Appendix B environmental technical specifications, it d. Discovery of significant radiological event off-      may be necessary to in-l'd-eftse                irepofrilntifie in
                                                              .RdgUoa_ Guide 1.21, "Measuring, Evaluating, and site occurring during transport of material for which the licensee was either shipper or consignee.                    Reporting Radioactivityin Solid Wastes and Releases of e. Unscheduled shutdowns expected to last for            Radioactive Materials in Liquid and Gaseous Effluents more than one week, regardless of cause.                      from Light-Water-Cooled Nuclear Power Plants," and f. Unusual releases of radioactive material from        Regulatory Guide 4.1 "Measuring and Reporting of the site boundary not reportable under other require-        Radioactivity in the Environs of Nuclear Power Plants,"
ments.                                                        in the technical specifications under the unique re- g. Failure of or damage to safety-related equip-        porting requirements section of the technical specifi- ment which need not be reported under item 2.a above,        cations.


1.16-6
&sect;40.64(a)        Transfer of Source Material                Promptly upon transfer.


APPENDIX A
&sect;40.64(a)       Receipt of , ource Material                 Within 10 days after material is received.
                                                            LICENSEE EVENT REPORT
                    CONTROL BLOCK            I I I I I I
                                              1                        6 LICENSEE                                                                        LICENSE        EVENT
                          NAME                              LICENSE NUMBER                              TYPE          TYPE
              FFI
                II       II            I      I 1 I-I          I ,1 I          iI-I
          9                          14      15                                            2    E
                                                                                                  26                      R
                                REPORT REPORT                                                    EVENT DATE
                                                              DOCKET NUMBER                                              REPORT DATE
                  CATEGORY TYPE SOURCE
              NT 7                59      .60        61                                68  69                  74
                                                                                                                      ~I    II 1 EVENT DESCRIPTION
  7    89                                                                                                                            80
    0o3111
  7    89
    0O41
  7    89                                                                                                                            80
    0o51
  7    89                                                                                                                            so
  7    8 9                                                            PRIME                                                          80
            SYSTEM      CAUSE                                      COMPONENT              COMPONENT
              CODE      CODE          COMPONENT CODE              SUPPLIER            MANUFACTURER      VIOLATION
              W          L    I  I                 I      WI        Li              I    I1    I          Li
  7    89    10          11        12                        17        43            44          47        48 CAUSE DESCRIPTION
                                                  I                                                                                      I
  7    89                                                                                                                            80
s 7 89 I
                                                                                                                                      80
                                                                              I IETHOD OF
w  1 FACILITY
              STATUS
                Li I
                                %POWER
                              I I I          jI
                                                          OTHER STATUS
                                                              _
                                                                            D ISCOVERY
                                                                                    i5      1 DISCOVERY DESCRIPTION
                                                                                                                                        I
  7    8        9            10          12      13                    44                4 16                                    a FORM OF                                                                45 ACTIVITY        CONTENT
            RELEASED OF RELEASE              AMOUNT OF ACTIVITY                                      LOCATION OF RELEASE
  [            L              L i                                                    45 I
                                                                                                                                      80
  7    8        9              10       11                                44 PERSONNEL EXPOSURES
  M          NUMBER          TYPE      DESCRIPTION
  7    8 9            11      12      13
                                                                                                                                      80  !
          PERSONNEL INJURIES
              NUMBER          DESCRIPTION                                                                                              I
                                                                                                                                        I
  7    8 9            11      12                                                                                                    80
          OFFSITE CONSEQUENCES
  7A 1 LOSS OR DAMAGE TO FACILITY
  78      TYPE
                    !o DESCRIPTION
        PUBLICITY
  78
  7    89
                                                                                                                                        0
        ADDITIONAL FACTORS
  7    89                                                                                                                            so
    19    I
  7    8 9                                                                                                                            8O
                    NAME*                                                                            PHONE:
                                                                        1.16-A-i


APPENDIX B
&sect;40.64(b)        Source Mateerial Inventory                  Within 30 days after June 30 of each year.
            STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION
                                                      Number of Personnel (> 100 mrem)                                           Total Man-Rem Contract Workers                                                    Contract Workers Work & Job Function                Station Employees  I    Utility Employees          and Others       Station Employees I Utility Employees          and Others Reactor Operations & Surveillance Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Routine Maintenance Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Inservice Inspection Maintenance Personnel Operating Personnel Health Physics Personnel
- Supervisory Personnel
- Engineering Personnel S Special Maintenance
- Maintenance Personnel Operating Personnel Health Physic s Personnel Supervisory Personnel Engineering Personnel Waste Processing Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Refueling Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel TOTAL
  Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Grand Total                      i __  _ _ _  _ _  _  __  _    _  __ _  _  _  _  _  _ _  _  _ _ J_
                                                                                                        I  _  _  _  _ _ _    I      _  _ _  _  _ _.1_I__ _  _  _  _ _  _


APPENDIX C
&sect;50.59(b)        Changes, Te sts, and Experiments            Annually or at Ahorter intervals as may be specified in the license.
                                                                        DOCKET NO.


UNIT
lear Material Status           Within 30 days after June 30 and December 31 of eachi
                                                                                DATE
   &sect;70.53            Special Nuc.
                                                                      COMPLETED BY
                                AVERAGE DAILY UNIT POWER LEVEL
  MONTH
           AVERAGE DAILY POWER LEVEL                          AVERAGE DAILY POWER LEVEL
  DAY                  (MWe-net)                      DAY                (MWe-net)
    1                                                  17
    2                                                  18
    3                                                  19
    4                                                  20
    5                                                  21
                                                        22
    7                                                  23
    8                                                  24
    9                                                  25
  10                                                  26
  11                                                  27
  12                                                  28
  13                                                  29
  14                                                  30
  15                                                  31
   16 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS
  On this form, list the average daily unit power level in MWe-net for each day in the reporting month.


. Compute to the nearest whole megawatt.
year.


These figures will be used to plot a graph for each reporting month. Note that by using maximum dependable capacity for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line). In such cases, the average daily unit powei output sheet should be footnoted to explain the apparent anomaly.
&sect;70.54          Transfer of Special Nuclear Material        Promptly upon transfer.


1.16-C-1
&sect;70.54          Receipt ofSSpecial Nuclear Material        Within IK days after material is received.


APPENDIX D
Appendix G to    Fracture To ughness                        On an individual-case basis at least 3 years prior to the
                                                                                                                        UNIT
    10 CFR Part 50                                              date when the predicted fracture toughness levels will no longer satisfy the requirements of section V.B. of Appendix G to 10 CFR Part 50.
                                                                                                                        DATE
                                                                                                                COMPLETED BY
                                                                                                                  DOCKET NO.-
OPERATING STATUS
  I. REPORTING PERIOD:                                                                                TTHROUGH
      HOURS IN REPORTING PERIOD:
  2.  CURRENTLY AUTHORIZED POWER LEVEL.(MWth)____                                                  - MAX. DEPENDABLE CAPACITY (MWe-NET)
  3.  LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED (IF ANY) (MWe-NET):
  4.  REASONS FOR RESTRICTION (IF ANY):
                                                                                                    THIS                              CUMULATIVE
                                                                                            REPORTING PERIOD          YR TO DATE        TO DATE
  5.  HOURS REACTOR WAS CRITICAL .............
  6.  REACTOR RESERVE SHUTDOWN HOURS                                            .......
  7.  HOURS GENERATOR ON LINE ...............
  8.  UNIT RESERVE SHUTDOWN HOURS ...........


===9. GROSS THERMAL ENERGY===
Appendix H to     Reactor Ve ssel Material Surveillance      Completion of tests after each capsule withdrawal.
      GENERATED (MWH) .          .....................
10.  GROSS ELECTRICAL ENERGY
      GENERATED (MWH)          ......................
11.  NET ELECTRICAL ENERGY GENERATED
      (M W H ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
12.  REACTOR AVAILABILITY FACTOR (1)                                    .........
13.  UNIT AVAILABILITY FACTOR (2)                            ............
14.  UNIT CAPACITY I-ACTOR (3)                    ...............
15.  UNIT FORCED OUTAGE RATE (4) ............
16.  SHUTDOWNS SCHEDULED TO BEGIN IN NEXT 6 MONTHS (STATE TYPE, DATE, AND DURATION OF EACH):
17.  IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
18.  UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) REPORT THE FOLLOWING:
                                                                                                                            DATE LAST      DATE
                                                                                                                            FORECAST     ACHIEVED
                                                                                            INITIAL CRITICALITY
                                                                                            INITIAL ELECTRICAL
                                                                                            POWER GENERATION
                                                                                            COMMERCIAL OPERATION
                                                                        HOURS=REACTOR WAS CRITICAL              X 100
(1)  REACTOR AVAILABILITY FACTOR
                                                                        HOURS IN REPORTING PERIOD
                                                                        HOURS =GENERATOR ON LINE                X 100
(2)    UNIT AVAILABILITY FACTOR
                                                                        HOURS IN REPORTING PERIOD
                                                                        NFT ELECTRICAL POWER GENERATED
(3)    UNIT CAPACITY FACTOR
                                                                          MAX. DEPENDABLE CAPACITY (MWe-NET)            X HOURS IN REPORTING PERIOD
                                                                        FORCED OUTAGE HOURS
(4)    UNIT FORCED OUTAGE RATE
                                                                        HOURS GENERATOR ON LINE + FORCED OUTAGE HOURS
                                                                                          1.16-D-1


. I . &#xfd;
10 CFR Part 50
                    INSTRUCTIONS FOR COMPLETING OPERATING DATA REPORT
  Appendix J to     Reactor Conntainment Building              Approximately 3 months following conduct of test.
                                                      (APPENDIX D)
This report is to be furnished each month by licensees.                8. Unit Reserve Shutdown Hours. The duration in The name, telephone number and extension of the                  hours that the unit was removed from service for preparer should be provided in the space labeled                  economic or similar reasons, but was available for
"Completed By." The instructions below are provided to            operation.


assist licensees in reporting the data consistently. The
10 CFR Part 50    Integrated L.eak Rate Test ITechnical Specifications
                                                                    9-10. Self Explanatory numbering of the instruction matches that used on the report format.                                                        11. Negative numbers should be used, if applicable.
                                                          1.16-S


12-15. For units still in the startup and power ascension test phase, items 12-15 should not be computed.
A
                                                                                                                                      4 . .
                                                                  TABLE II
                                REPORTING SUMMARY-NON ROUTINE REPORTS
                                                                                                    Initial Writtan Report Within Requirement        Report                                                Notification          10 days      15 days 30 days      3 mo T'I                  Abnormal Occurrence                            Within 24 hours            X
TS                    Unusual Events                                                                                  X
                                                                                                                      X
&sect;20.405              Overexposures and Excessive Levels of Radiation and Concentration of Radioactive Material
&sect;20.402              Theft or Loss of Material                      Immediately                                      X
&sect;20.403(a)          Severe Accident lnvolhiir Licensed              Imnediately Material
&sect;20.403(b)          Accident        Involving        Licensed      Within 24 hours Material
&sect;40.64(c)            Theft or Unlawful Diversion of                  Prompt ly                              X
                    Source Material
&sect; 50.59(d)            Authorization      of Cl,            "cs,.
                                                          Tesrre*.
                    and Experiments
&sect; 70.52              Accidential Criticality or Loss of              IP'rotmplvl Special Nuclear Material
&sect; 73.42              Unaccounted for Shipments.                      I tmnmediately                          X
                    Suspected Theft. or Unlawful Diversion of Special Nuclear Material TS                  Special                                                                                                      V.


OPERATING STATUS                                                  Instead, enter N/A in the current month column. These four factors should be computed starting at the time the
'Technical Specifications.
      1. Reporting Period. The Period normally will be            unit is declared to be in commercial operation. The from 0001 of the first day through 2400 of the last day          cumulative figures in the second and third columns of the calendar month. There may be some slight                  should be based on commercial operation as a starting variations, however, and this item should be used to              date. However, units already in commercial operation, indicate when such variations occur. Successive monthly          for which cumulative figures have been based on reports should be consistent; i.e., no gaps in time.              different starting dates, need not recalculate the Report as hour, year, month, day using 24-hour clock              cumulative figures.


(0001, 750814 for 12:01 a.m. on August 14, 1975).                      12. Reactor Availability      Factor. Compute by Hours in reporting period should be calculated from              dividing Hours Reactor was Critical (Item 5) by Hours in report period.                                                    Report Period (from Item 1). Express as percent, to
AEC authorization is required prior u) perfokrniinc a chune. tcsi. ,r e\perime1nt in tlis L.lteyorV.
      2. For the "net" figure, use Maximum Dependable            nearest tenth of a percent. During months when the unit Capacity. Maximum Dependable Capacity is defined as              is shut down for the entire period due to non-reactor the dependable main-unit capacity, winter or summer,              problems, enter "Not Applicable." Do not include whichever is smaller.                                            reserve shutdown hours in the calculation.


3. Note that this item is applicable only if                      13. Unit Availability Factor. Compute by dividing restrictions on the power level are in effect.-Short-term        Hours Generator On Line (Item 7) by Hours in Report (less than one month) limitations on power level need            Period (from Item 1). Express as percent, to nearest not be presented in this item, since one of the important        tenth of a percent. Do not include reserve shutdown purposes of the item is to determine if, and at what              hours in the calculation.
3 Special reports covering inspections, tests. and maintenance that are appropriate to assure safe operaliol of'i lt fIcliliry. Tile frequency and content of these special reports are determined on an individual case basis and designated in tis. i echinic.rl Sw.cifw.'ation5.


power level, a restricted power level line should be                  14. Unit Capacity Factor. Compute by dividing Net drawn on the chart of average daily reactor power.               Electrical Energy Generated (Item II) by the product of Since this information is used to develop figures        Maximum Dependable Capacity (MWe-net) (Item 2)
Such reports include inservice inspection. tendon sunreillance procrani study, fuel inspection. and contanirnment s*lr    ur:l :c'.ls.
on capacity lost due to restrictions and because most            times Hours in Report Period (from Item I). Express as users of the "Operating Plant Status Report" are                  percent, to the nearest tenth of a percent.


primarily interested in energy actually fed to the
I .16-6
                                                                      15. Unit Forced Outage Rate. Compute by dividing distribution system, we request that this figure be Total Forced Outage Hours (from shutdown table, expressed in MWe (net) in spite of the fact that that figure must be derived from MWth or percent power.                Appendix E) by the sum of flours Generator On Line (item 7) plus Total Forced Outage Hours (Appendix E).
    4. Reasons for Restriction (if any). If item 3 is            Express as percent, to nearest tenth of a percent.


used, explain in item 4. Brief narrative is acceptable. Cite references as appropriate. Indicate whether restrictions               16. Shutdowns Scheduled to Begin in Next 6 Months. Include type (refueling, maintenance, other),
9 A
are self-imposed or are regulatory requirements. Be as proposed date of start of shutdown and proposed length specific as possible within space limitations. Plants in of shutdown. It is recognized that shutdowns may be startup and power ascension test phase should be scheduled between reports and that this item may not be identified here.
  t
          .  -  a
0
                                                            APPENDIX A
                        STANDARD FORMAT FOR REPORTING ABNORMAL OCCURRENCES
            The standard format for submission of abnormal            information included, the format for abnormal occurrence reports (AOR) identifies the principal                occurrence reports presented below should he usci and information that should be contained in a completed                the information requested should be submitted when AOR and gives a' format for presenting it. In the course          applicable. If investigation is not complete by the time of reviewing past AOR's the AEC Regulatory staff has               the initial report is submitted, the licensee should so found a wide variance in the type and detail of                   indicate and give estimated time when a supplemental information reported. To assure that AOR's submitted              report will be submitted.


all inclusive. Be as accurate as possible as of the date the
are consistent both in format and in the principal STANDARD FORMAT FOR ABNORMAL OCCURRENCE REPORTS
       5. Self Explanatory                                        report is prepared.
      Report Number: . (1)                                            Description of Occurrence:      (6)
      Report Date:      (2a)                                          Designation of Apparent Cause of Occurrence:    (7)
       Occurrence Date:        (2b)                                          Design Manufacture Facility:      (3)                                                      Installation/Construction
                                                                          -Operator Identification of OccUrrence:        (4)                          -Procedure
                                                                          -Unusual Service Condition Including Environmental Conditions Prior to Occurrence:          (5)
                                                                          -Component Failure
                                                                          -Other (specify)
        -      Steady-State Power
      -      Hot Standby
      -      Cold Shutdown
      -      Refueling Shutdown                                      Analysis of Occurrence:    (8)
      -      Routine Startup Operation
      -      Routine Shutdown Operation                                Corrective Action:    (9)
              Load Changes During Routine Power Operation
      -      Other (Specify)                                          Failure Data:    (10)
                                                  NOTES TO AOR STANDARD FORMAT
      I. Report Number: Abnormal occurrence reports                      2. Report Date: Date of (a) report submitted and (b)
            should be numbered sequentially on a calendar-year                occurrence.


6. Reactor Reserve Shutdown Hours. The duration                  17. Self Explanatory.
basis for each facility (or each unit of a multi-unit site) using the facility (unit) docket number as the        3. Facility: Name and location of facility.


in hours that the reactor was removed from service for
principal identifier (e.g., Docket NumberJYear-Sequential Number in calendar year).
                                                                      18. Self -Explanatory. Note, however, that this administrative or other reasons but was available for information is requested for all units in startup and operation.                                                       power ascension test status, and is not required for units
            Supplementary reports should be numbered using              4. Identification of Occurrence: The abnotmal alphabetical identifying letters following the                   occurrence should be identified by a short title'
      7. Self Explanatory                                        already in commercial operation.
            principal report number (e.g., Docket                            which identifies the type of abnormal occurrence Number/Year-Sequential Number in calendar                        and the system, component. or even, involved.


'1.16-D-2
year-alphabetical letter identifying supplementary              (Regulatory Position C.2.a.(I) should be used as a report.)                                                        guide for listing the type of abnorml occurrence.)
                                                                  1.16-7


0                                              APPENDIX E                              DOCKET NO.
a S. Conditions Prior to Occurrence: Thie applicable                        structures.


UNIT SHUTDOWNS                              UNIT NAME
c:apf ion should be used followed by a description              e.  Personnel    injuries.
                                                                                                  DATE
                                                                                      COMPLETED BY
                                        REPORT MONTH
                    TYPE                                METHOD OF
        -        F-FORCED  DURATION                  SHUTTING DOWN
    NO.  DATE. S-SCHEDULED  (HOURS) REASON (1)      THE REACTOR (2)        CORRECTIVE ACTIONS/COMMENTS
ON
                                                                      (1) REASON                        (2) METHOD
                                                                          A EQUIPMENT FAILURE (EXPLAIN)    I --MANUAL
                                                                          B MAINT. OR TEST                  2 -MANUAL
                                                                          C REFUELING                          SCRAM
                                                                          D-REGULATORY RESTRICTION          3 --AUTOMATIC
                                                                          E- OPERATOR TRAINING AND*            SCRAM
                                                                                LICENSE EXAMINATION
                                                                          F- ADMINISTRATIVE
                                                                          G- OPERATIONAL ERROR
                                                                                  (EXPLAIN)
                                                                          H -OTHER (EXPLAIN)
  SUMMARY:


INSTRUCTIONS FOR COMPLETING MONTHLY UNIT SHUTDOWN REPORTS
of plant status prior to tie abnormal occurrence.                f.   Personnel exposures.
                                                          (APPENDIX E)
UNIT SHUTDOWNS                                                        It is recognized that some judgment is required in categorizing shutdowns in this way. In general, a forced This section should describe all plant shutdowns                 shutdown is one that would not have been completed in during the report period. In addition, it should be the              the absence of the condition for which corrective action source of e-planation of significant dips in average                  was taken.


power levels (Appendix C). Each significant reduction in power level (greater than 20% reduction in average daily              DURATION (HOURS)
Major plant parameters should be included.                       g.   Quinmtity and composition            of   radioactive materials released.
power level for the preceding 24 hours) should be noted, even though the unit may not have been shut down Self explanatory. When a shutdown extends beyond completely.' For such reductions in power level, the the end of a report period, count only the time to the shutdown duration should be zero, the method of end of the report period and pick up the ensuing shutting down the reactor should be N/A, and the down time in the following report periods. Report Comments column should explain. The Comments duration of outages or significant reductions in power column should be used to provide any needed                          rounded to the nearest tenth of an hour to facilitate explanation not adequately described by the coded summation.


columns. Please do not add to the list of codes or legends now furnished. Similarly, do not add additional columns.
6. Description of Occurrence: A chronological                        Ih. The consequences        cr potential colsequnclies sequence of events should be described in an                          &#xfd;from the     standpoint    of public    healfli  and objective manner. The following should be                              safety.


REASON
included:
                                                                          Categorize by letter designation in accordance with NUMBER                                                                the table appearing on the report form. If none of the specified categories can be used, supply brief comments.
  a. Method of detection and time of detection.                9. Corrective Action:'          The following      informalion b. Step-by.step sequoence of events identif'ying all              should he provided:
        protection system :tctions and operator actions            a.  Correclive action lakcn (or to he laken) to to hrmig fhc sitation under control.                            correct tile abnormal occurrence.


This column should indicate the sequential number assigned to each shutdown or significant reduction in power for that calendar year. When a shutdown or                     METHOD OF SHUTTING DOWN THE REACTOR
It. Corrective action taketn (or to he i;keinL) hn
significant power reduction begins in one report period and ends in another, an entry should be made for both                      Categorize by number designation in accordance report periods to be sure all shutdowns or significant              with the table appearing on the report form. If none of power reductions are reported.                                        the specified categories can be used, supply brief comments.
7. Designation of Apparent Cause of Occurrence: The                      prevent    repetilion of the occurreince and          )I
  single apparent cause should be identified and                        similar occurrences.


DATE
narrated. When other causes contributed to the abnormal occurrence. the narrative of the apparent          10. Failure Data: Where equipment failure is cause of cause should discuss fully the single cause assigned              the occurrence or equipment failed as a result o1f and the contributing causes assigned.                             tile occurrence, the following inforilmlion should be provided:
                                                                      CORRECTIVE ACTIONS/COMMENTS
8. Analysis of Occurrence: The abnormal occurrence                  a. Record of previous failures :rmd inallfunctions it should be analyzed for safety implications. The                        the affected systems and components or ot analysis of effect." and the attendant consequences                    similar equipment.
    This column should indicate the date of the start of each shutdown or significant power reduction. Report as Use this column to amplify or explain as necessary.


year, month, and day. August 14., 1975 would be Where appropriate, the Comments column entries should reported as 750814. When a shutdown or significant power reduction begins in one report period and ends in              provide identification of each shutdown or significant power reduction that occurs as a direct result of an another, an entry should be made for both report periods to be sure all shutdowns or significant power                abnormal occurrence on which a report has been or will reductions are reported.                                             be submitted. (This information may not be imme- diately evident for all such shutdowns, of course, since further investigation may be required to ascertain TYPE                                                                  whether or not an abnormal occurrence was involved.)
should include tile following information, as                     b.   Equipment      identification (e.g..      componcMtt.
                                                                      When a direct correlation can be made between a given Use "F" or "S'" to indicate either "Forced" or                  shutdown and a specific abnormal occurrence report, the
"Scheduled,"     respectively, for each shutdown or                  Comments column entry, should state the abnormal signific.ant power reduction. Forced shutdowns include                occurrence report number and date.


those required to be initiated by no later than the weekend following discovery of an off-normal condition.
applicable:                                                            mnufacturer. natile plate data).
  a. Maximum and ,minimum conditions during
                                                                    'The    cautse of [tie occurrence  is described  in Item 7.


SUMMARY INSTRUCTIONS
transients.                                            "Designation of Apparent Cause of Occurrence." and Ihc b. Equipment malfunction.                                   action taken to bring the situation under control is disetss'cd c. Operator error.                                          in Item 6, "Description of Occurrence." Tlihest items should d. Damage to systems. components. and                        not be repeated in this discussion.
'Note that this differs from the Edison Electric Institute (EEl)
definitions of "Forced Partial Outage" and "Scheduled Partial            Write a brief summary (i.e., 3 to 4 sentences)
Outage." For these terms, EEl uscs a change of 30 MW as the break point. For larger power reactors, 30 MW is too small a        description of the highlights of operation of the unit for change to %%arrantexplanation.                                       the reporting month.


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Revision as of 00:15, 20 March 2020

Reporting of Operating Information
ML13350A370
Person / Time
Issue date: 10/31/1973
From:
US Atomic Energy Commission (AEC)
To:
References
RG-1.016, Rev. 1
Download: ML13350A370 (8)
v • d • e


-I - Revision 1 Revision 1 October 1973 Se US. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE OF REGULATORY STANDARDS

GUIDE

REGULATORY GUIDE 1.16 REPORTING OF OPERATING INFORMATION

A. INTRODUCTION

the ('omliission's regulations is also included. The AEI'

Regulatory staff has ieviewed Ihe types sf inorloratislat SCction 50.36. "TTechnical Specifications." of 10 needed. Based oln !tis review and a review irf licensees'

CFR Part 50, "Licensing ot Production and Utilizationi current reporting pt igrai.; the staff has developed Facilities," requires that easch applicant for a license guidelines fotr such repirtint.. Thik ituidc presents an authorizing operation of a nuclear power plant include acceptable reporting prourainn I ol powel reactor in his applica tion proposed technical specifications. licensees. Ta hles I and II o1 this guide are coilpilaliotm.s These technical specifications as approved by the AE-C of tinme limits or frequency :inlervals [tr subhnlitting are incorrporated into tire facility license and are routline and nonroutline report:,. Acceptable repoirtlin1 conditions oif the license. The technical specifications for programs tor radioactive eflluents and environnmen.tal nuclear power plants include a section on reporting monitoring are presented in Regulatory Guides 1.21 requirements. In addition to the reporting requirements (Safety Gtmide 211. "Measuring and Reporting oft'

necessary for compliance with the technical Effluents from Nuclear Pow\ver and 4.1

lait<.

specifications of the license, there are specific reporting "'Measuring and Reportine ofi' R:idioct'livilt itl the requirements included in Part 50 as well as in Parts 20. Environs of Nuclear Power P1lhnts."' respectively.

40. 70. and 73 of Title 10. For the convenience of licensees, these specific reporting requirements are Significant differences in Revision I of this guide included in the reporting program described in this from Regulatory Guide 1.16o formerly Safety Guide 16)

guide. Each report discussed in this guide is either dated October 27, 1971 are:

required by AEC regulations or is normally specified in licensees' technical specifications. In some cases this I. Extensive quoting of the Commission*, regulations program may need to be supplemented or modified has been deleted. References to the appropriate portiots because of unique plant design features or other factors. of the Commission's regulations are included itt Tables I

The need for a supplemental or modified program will and !1 of this guide.

be determined on an individual-case basis. The Advisory Committee on Reactor S'feguards has heen consulted 2. For ease of reference the reporting summary table concerning this guide and has concurred in the included in the original guide has been divided into two regulatory position. tables (Routine Reports and Nonroutine Reports)

B. DISCUSSION

3. Reporting requirements have been updated ti reflect changes in the Comnmission's regulations and the reports required by the technical specifications.

The information provided in the reports discussed herein should be sufficient to permit an assessment by the Commission of all safety-related activities during and 4. Appendix A of this guide. "Standard iormtatl I't following the startup of the facility. Reporting Abnorinal Occuirrences." ha,: h'etn added to give guidance to licensees suhmittinzg abnormal occurrence reports.

In addition to those reports that relate to the safety of operation of the plant, the information on nuclear "Lines indicatc substantive chaivs O'wn10plcvihitls isslie.

materials safeguards that must be reported pursuant to USAEC REGULATORY GUIDES Copies of published guides may be obtained by routs' ,ldicanig the divisions desired to the US. Atomic Energy Commission. Washinglon. D.C. 20545.

pleguletory Guides are sisued to describe and make avrtable to the public Attention: Director of Regulatory Standards. Comments and wu9grtiodls tfo methods acceptable to thP AEC Regulatory stalf ot Implementing &peailicparis of ImprOvements In these guides ere encourAged and shotrid be ient to the Secretary the Comtn4tion's regulations. to delineate technijuest used by the Staff in of the Commission, U.S. Atomic Energy Commission. W*%hinl.to. D.C. 20545.

evaluating specific problems or potiulated accidents, or to provide guidance to Attention: Chief. Public Proceedings Stafl.

ipplicants. Regulatory Guides are not substitutes for regulations and compliance with them ihnot required. Methods and eolutions different from those set oul In I he guides are issued in the following ten broad dcviSons:

the guides will be acceptable If they provide a basit for the findings requisi Power Reor

2. RePearch and Test Reactors

7. Products

6. T samotatne the issuance or continuance of a permit or license by the Commission.

3. Fuels ant] Materials Facilities

8. Occuttationiri Hal h

4, Envitonmntol and Siting 9. Ar-rtruit Rr.v,ewv Published guides will be revised periodically, as a~ptopriate, to accommodalte 5. Materialsand Plant Protection 10. Genetal commentS and to reflect new information or eaperience.

,, ,III I*1]11 II * III- - - -

C. REGULATORY POSITION

(d) a progress and status report oir airy items identified as requiring additional inforitation The following reporting program should be used to during tire operating license review or during the startup implement the reportintg requirements of 10 CFR Parts of tlie facility, including ilemns discussed in tile AEC's

20, 40. 50. 70. 73, and teporting requirenments imposed Safely Evaluation Repmrt and Supplements, items on by the AEC as license conditions. including those reports which additional information was required as a required by thie tclnlical specilrCations. conrdition of the license. and itemrs identified in the licensee's st:artup report: and

1. Routine Reports (e) a report of measured in-plant radiation levels which are greater thiran those estimated irr the final a. Operations Reports' safety analysis report by a factor of two or more.

I I ) Startup Report. A summary. report of plant (3) Semiannual Operating Reports? Routine startot) and power escalation testing should he submittcd operating reports covering tire operation o tIrh pre2 hus I'o0lowitrg reccipi t it' ai upctatintg license, tollowing an (I mionths should be subtrmitted witiirt 60 days after amendment it the licenise involving -a planned increase in Jartnuary I and Jtly I of each year. The initial report power level. ft,..owin iv the iLnstall.'tinn of rrel il has if shtitld he stthlirited Withint 00 days after the cild iI' the different design ur hlas been nranuutfactrrred by a different first six-nmonth period during which initial criricalily fuel supplier. or fIOllowing modi fications dial nay haive took place. Fa ch report should inelnrde the followirrg:

signifilcantly ahlrred the nuclear. thermal. or hydranlic perftorniance iI"Ithe pl:ant. The report should include a (a) Operations Sumrnmar'. A stinrirary of description of The :mc:c*scIcd ';iltiues tit' the ocerating operating experience occurring during the reportiog conditions or ctharacteristics obtained during the test period that relates to tire s:icuoperation of the facility.

progratn and a comnparison of these values with design including a sumnmary of:

predictions and specifications. Any corrective actions (i) changes in facility design.

that Were requ.ired to obtain sattisfactlotv operarior (it) performance characteristics (e.g..

should also he' dcr itwcd. Sr rtrup reporls sluimld lie eqttipreti t ;tnid fuel per formlance),

slrblnlilrled willitm I1) 10 clays following cormpletion of (iii) changes in) operating procedutres Ire stalt tip test ptoigra in. (2) 90 days following which were necessitated by (i) and (ii) above or which resturnpli crrit ior c ntten nt o1f c rommerciaI po'wer otherwise were required to improve thie saklty of operation. or 31 t ) nronths following initial criticality. operations, whichever is earliest. If thie Startutp Report does not (iv) results of surveillance tests and cover all tihrec cverrts. i.. initiial criticalily. cotmlpletion inspections required by the licensee's technical ot S :crl tip t Cst plro ra iii. rod resl rillpt loll or speciftications.

ce tonmterncete. *of :o Inetrrc ial poe'r operatiion. (v) the results of aniy periodic Suplplementa'ry rep.crts Slhou.ld he srtbitritted at least cottainment leak rate tests performed during the every lthrce rir*ithl trit ;i ll! hi c evonts are t.orrpleted. reporting period.

(vi) a brief suimmary of tirosk cihtanges.

(2) First Year Operaton Report. A report tests. and experiments requiring auLthorization from the sh1trld hC subnrittled wit hin 60 days aftier completion of Commission purtntant to 10 CMR 50.59(a), and the first year oit operalion. This .tar begims oc (vii) any chanrges in thie p1lnt operating coltplet ion tt'oall three evetlt s listed in C.;.a.i i ). This staff for thiose positions designated as key stipervisory report mtay he incorpor:ated into tile semiatrtrtl personniel positions in the technical specificairs.

olperatrino relport rard shurld cover tire following:

(:ill ;m ,nv:ltr;!tit1In '; plhrtl p*rltl'lrr ltcc hi (b) Power Generation. A sumnnmary of dale in corinlprisim wi! Ii 'sicti !tiedicticlns and powet generated during the reporting period including:

S1ilic.l jihltilsl'* O: iI ,ilil .** (iM gross thermal power geterated (itn MWI 1).

subriitied Witlh the license application i1" measured (ii) gross electrical power generated operating characteristics indicate that there may be (in MWH),

substantiialvariance fronm prior analyses:2 (iii) number of iours tire reactor was (c) an assessrenrt of file performance of critica!,

strtctures. sysletrs. and components iml'-rtant to (iv) number of hours the generator safety: was on line, and (v) histogram of thermal power vs.

iti, Ca, thill L l.!,. .1titihctcld bheS.tllrith: ill writirg tI0 t if e.

Ie I)reclror orI rth e ;Ipprlrltialte AViC Re utailort - (i,,cration n Regionial Office.

'A sinrde subliimr itl may be imadrde for a multiple facility

2I'rciously r it rit tedl sal  % ;! raysi.s repo r r i V. mat iim. The stticrrthittal shiould corritine tinrow. eclions Irh are inLccrloritlcl hb t eretilrce. comllrrrlrn iI all I'acilitics at ilre station.

I .I0c-2

I *

(c) Shutdowns. Descriptive material (g) Occupational Personnel Radiation covering all outages occurring during the reporting Exposure period. For each outage, information should be provided oil: i) A tabulation of 0i1e titinher Of (i) tile cause of the outage, occupational personnel exposures for plan' operations (ii) the inethud of shutting down the personnel (permanent and temporary) in the following

]reactor; e.g.. trip, automatic rundown, or manually exposure increments for the reporting period: less thatn controlled deliberate shutdown' 100 mrerm, 100-250 ortem. 250-500 ntoem. 5001-750

(iii) duration of the outage (in hours), morem, 750-1000 mrem. 1-2 rem. 2.3 retn. 3.4 rem. 4-S

(iv) plant status during the outage' rem, 5.6 rem, and greater than 6 remi.

e.g.. cold shutdown or hot standby, and (v) corrective action taken to prevent (ii) A tabulation of the nurniter ot'

repetition, if appropriate. personnel receiving more than 500 mrem exposure in the reporting period according to duty function le.g..

(d) Maintenance. A discussion of routine plant surveillance and inspection (regular duty),

corrective maintenance (excluding preventive routine plant maintenance, special plant mainten:itce maintenance) performed during the reporting period on (describe maintenance). routine fueling operation.

safety-related systems and components4 and on systems special refueling (,peration (describe opetation*. and and components that reduce or prevent the release of other job-related exposures.]

radioactive materials to the environs. For any malfunction for which corrective maintenance was (iii) A tabulation annually of the required, information should be provided on: number of personnel receiving more than 3 rein atnd fie (i) t he system or component major cause(s).

involved, (ii) the cause of the malfunction. (hi) FSAR Changes. Submission of revised (iii) the results and effect on saf. FSAR pages on a replacement page basis appropriately operation. and r7epared for direct insertion into the applicable FSAIR

(iv) corrective action taken to prevent section and describing all safety.related chaniges in'

repetition. facility design. method of operation. revised safety or transient analysis. or f:,cility equipment additiots. Also a (e) Changes, Tests and Experiments. A listing of effective pages by date of revision or revisiotn brief description and the summary of the safety number should be submitted.

evaluation for those changes, tests, and experiments, carried out without prior Commission approval pursuant b. Additional Routine Reporting Requirements.

to the provisions of IOCFR 50.59(b). Table 1 lists routine reports required by 10 CFR Parts

20. 40, 50. and 70. including those listed in Regulatory (f) Primary Coolant Chemistry. A Position C.I .a.

tabulation on a monthly basis of the maximum. average, and minimum values for the following primary coolant system parameters: 2. Nonroutine Reports (i) Gross radioactivity in pCi/ml.

(ii) Suspended solids in parts per a. Reporting of Abnormal Events

(1) Abnormal Occurrence Reports. A

million.

notification must be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone (iii) Gross tritium in pCi/ml.

(iv) Iodine 131 in pCi/ml, and telegraph to the Director of the appropriate AlFC

(v) Ratio of Iodine-131 to Regulatory Operations Regional Office. (cc to the Iodine-I133. Director of Licensing) followed by a written report wihrin 10 days to the Director of the appropriate AlEC

(vi) Hydrogen in cc per kg.

(vii) Lithium in parts per million. Regulatory Operations Regional Office in the event of (viii) Boron-lO in parts per million. an abnormal occurrence.

(ix) Oxygen-16 in parts per billion, Appendix A of this guide, "Standaid (x) Chloride in parts per million, and Format for Reporting Abnormal Occurrences.- should (xi) pH at 250 C.

be used as guidance when submitting abnotmtal occurrence reports.

4Those plant features necessary to assure the integrity of the reactor coolant pressure boundary. the capability to shut Abnormal occurrences are defined in the down the reactor and maintain it in a jal'vo shtdown condition. definitions section of the licensee's technical consequences of1 or the capability to prevent or miti~oc tite specifications and usually include, as a miniutitll, items accidents which could result in o.itc e,'i.sures comparable to the guideline exposures of 10 CFR Part 100. (a) through (h) of this paragraph.

1 1 -3

(a) A safety. systeil setting- :ess (2) Reporting of Unusual Events. A written conlservative titan the limiting setting, established in the report should be forwarded within 30 days to the technical specifications. Director of t(ie appropriate AEC Regulatory Operations (b) Conditions which result in a limiting Regional Office, in the event of:

condition for operations established in the technical (a) Discovery of any substantial errors in specilfications not being met. the transient or accident analyses, or in the methods

'0 Abnormal degradation of one of thie used for such aitalyses. as described in the Safety several boundaries designed to contain radioactive Analysis Report or in the bases for the technical materials. specificat ions.

(d) An unplanned or uncontiolled release (b) Discovery of any substantial variance of radioactive material from the site boundary. from performance specifications contained in the (e) Uncontrolled or unanticipated changes technical specifications or in thle Safety Analysis Report.

in reactivity "qual to or greater than 1%Akikk. (c) Discovery of any condition involving a

(') Incidents or conditions which ipossible single failure which. for a system intended to be prevented or could have prevented the performance of designed against assumed single failures. could result in a thle intended safely function of an engineered safely loss of the capability Of the system to perform its safety feature system or of the reactor protection system. 'loun ion.

(g) Observed inadequacies in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause b. Additional Nonroutine Reporting the existence or development of an unsafe condition in Requirements connection with tile opelation of the plant.

(h) Conditions arising from natural of Table II lists nonroutine reports required by 10

man-made events that affect or threaten to affect the CFR Parts 20. 40, 50, 70, and 73. including those listed sale operation of the plant. in Regulatory Position C.2.a.

5A~defined in 10CF]R 50.36(c).

i

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0e TA8LE I

REPORTING SUMMARY-ROUTINE REPORTS*

Requirement Report Timing of Submittal T'SI Startup Within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3)

9 months following initial criticality. whiiclhever is earhest.

If all thrce events arc not completed. supplementairy reports every 3 monu~ths.

TS First Year ()perat.on Within 60 days after completion of the first yeat of operation.

TS Semiannual Within 60 days after January Iand July I of each year.

§20.407 Personnel Exposure and Monitoring Within first quarter of each calendar year.

§20.408 Personnel Exposure on Termination of Within 30 days after the exposure of the individual has Employmenit or Work been determined or 90 days after date of termination of employment or work assignment. whichever is earlier.

§40.64(a) Transfer of Source Material Promptly upon transfer.

§40.64(a) Receipt of , ource Material Within 10 days after material is received.

§40.64(b) Source Mateerial Inventory Within 30 days after June 30 of each year.

§50.59(b) Changes, Te sts, and Experiments Annually or at Ahorter intervals as may be specified in the license.

lear Material Status Within 30 days after June 30 and December 31 of eachi

§70.53 Special Nuc.

year.

§70.54 Transfer of Special Nuclear Material Promptly upon transfer.

§70.54 Receipt ofSSpecial Nuclear Material Within IK days after material is received.

Appendix G to Fracture To ughness On an individual-case basis at least 3 years prior to the

10 CFR Part 50 date when the predicted fracture toughness levels will no longer satisfy the requirements of section V.B. of Appendix G to 10 CFR Part 50.

Appendix H to Reactor Ve ssel Material Surveillance Completion of tests after each capsule withdrawal.

10 CFR Part 50

Appendix J to Reactor Conntainment Building Approximately 3 months following conduct of test.

10 CFR Part 50 Integrated L.eak Rate Test ITechnical Specifications

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A

4 . .

TABLE II

REPORTING SUMMARY-NON ROUTINE REPORTS

Initial Writtan Report Within Requirement Report Notification 10 days 15 days 30 days 3 mo T'I Abnormal Occurrence Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> X

TS Unusual Events X

X

§20.405 Overexposures and Excessive Levels of Radiation and Concentration of Radioactive Material

§20.402 Theft or Loss of Material Immediately X

§20.403(a) Severe Accident lnvolhiir Licensed Imnediately Material

§20.403(b) Accident Involving Licensed Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Material

§40.64(c) Theft or Unlawful Diversion of Prompt ly X

Source Material

§ 50.59(d) Authorization of Cl, "cs,.

Tesrre*.

and Experiments

§ 70.52 Accidential Criticality or Loss of IP'rotmplvl Special Nuclear Material

§ 73.42 Unaccounted for Shipments. I tmnmediately X

Suspected Theft. or Unlawful Diversion of Special Nuclear Material TS Special V.

'Technical Specifications.

AEC authorization is required prior u) perfokrniinc a chune. tcsi. ,r e\perime1nt in tlis L.lteyorV.

3 Special reports covering inspections, tests. and maintenance that are appropriate to assure safe operaliol of'i lt fIcliliry. Tile frequency and content of these special reports are determined on an individual case basis and designated in tis. i echinic.rl Sw.cifw.'ation5.

Such reports include inservice inspection. tendon sunreillance procrani study, fuel inspection. and contanirnment s*lr ur:l :c'.ls.

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9 A

t

. - a

0

APPENDIX A

STANDARD FORMAT FOR REPORTING ABNORMAL OCCURRENCES

The standard format for submission of abnormal information included, the format for abnormal occurrence reports (AOR) identifies the principal occurrence reports presented below should he usci and information that should be contained in a completed the information requested should be submitted when AOR and gives a' format for presenting it. In the course applicable. If investigation is not complete by the time of reviewing past AOR's the AEC Regulatory staff has the initial report is submitted, the licensee should so found a wide variance in the type and detail of indicate and give estimated time when a supplemental information reported. To assure that AOR's submitted report will be submitted.

are consistent both in format and in the principal STANDARD FORMAT FOR ABNORMAL OCCURRENCE REPORTS

Report Number: . (1) Description of Occurrence: (6)

Report Date: (2a) Designation of Apparent Cause of Occurrence: (7)

Occurrence Date: (2b) Design Manufacture Facility: (3) Installation/Construction

-Operator Identification of OccUrrence: (4) -Procedure

-Unusual Service Condition Including Environmental Conditions Prior to Occurrence: (5)

-Component Failure

-Other (specify)

- Steady-State Power

- Hot Standby

- Cold Shutdown

- Refueling Shutdown Analysis of Occurrence: (8)

- Routine Startup Operation

- Routine Shutdown Operation Corrective Action: (9)

Load Changes During Routine Power Operation

- Other (Specify) Failure Data: (10)

NOTES TO AOR STANDARD FORMAT

I. Report Number: Abnormal occurrence reports 2. Report Date: Date of (a) report submitted and (b)

should be numbered sequentially on a calendar-year occurrence.

basis for each facility (or each unit of a multi-unit site) using the facility (unit) docket number as the 3. Facility: Name and location of facility.

principal identifier (e.g., Docket NumberJYear-Sequential Number in calendar year).

Supplementary reports should be numbered using 4. Identification of Occurrence: The abnotmal alphabetical identifying letters following the occurrence should be identified by a short title'

principal report number (e.g., Docket which identifies the type of abnormal occurrence Number/Year-Sequential Number in calendar and the system, component. or even, involved.

year-alphabetical letter identifying supplementary (Regulatory Position C.2.a.(I) should be used as a report.) guide for listing the type of abnorml occurrence.)

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a S. Conditions Prior to Occurrence: Thie applicable structures.

c:apf ion should be used followed by a description e. Personnel injuries.

of plant status prior to tie abnormal occurrence. f. Personnel exposures.

Major plant parameters should be included. g. Quinmtity and composition of radioactive materials released.

6. Description of Occurrence: A chronological Ih. The consequences cr potential colsequnclies sequence of events should be described in an ýfrom the standpoint of public healfli and objective manner. The following should be safety.

included:

a. Method of detection and time of detection. 9. Corrective Action:' The following informalion b. Step-by.step sequoence of events identif'ying all should he provided:

protection system :tctions and operator actions a. Correclive action lakcn (or to he laken) to to hrmig fhc sitation under control. correct tile abnormal occurrence.

It. Corrective action taketn (or to he i;keinL) hn

7. Designation of Apparent Cause of Occurrence: The prevent repetilion of the occurreince and )I

single apparent cause should be identified and similar occurrences.

narrated. When other causes contributed to the abnormal occurrence. the narrative of the apparent 10. Failure Data: Where equipment failure is cause of cause should discuss fully the single cause assigned the occurrence or equipment failed as a result o1f and the contributing causes assigned. tile occurrence, the following inforilmlion should be provided:

8. Analysis of Occurrence: The abnormal occurrence a. Record of previous failures :rmd inallfunctions it should be analyzed for safety implications. The the affected systems and components or ot analysis of effect." and the attendant consequences similar equipment.

should include tile following information, as b. Equipment identification (e.g.. componcMtt.

applicable: mnufacturer. natile plate data).

a. Maximum and ,minimum conditions during

'The cautse of [tie occurrence is described in Item 7.

transients. "Designation of Apparent Cause of Occurrence." and Ihc b. Equipment malfunction. action taken to bring the situation under control is disetss'cd c. Operator error. in Item 6, "Description of Occurrence." Tlihest items should d. Damage to systems. components. and not be repeated in this discussion.

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