Regulatory Guide 1.16: Difference between revisions

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{{Adams
{{Adams
| number = ML003739954
| number = ML13350A370
| issue date = 08/31/1975
| 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 =  
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| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.16, Rev 4
| document report number = RG-1.016, Rev. 1
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 15
| page count = 8
}}
}}
{{#Wiki_filter:Reviion 4 U.S. NUCLEAR REGULATORY  
{{#Wiki_filter:-I -Revision 1 Se US. ATOMIC ENERGY COMMISSION
COMMISSION
REGULATORY
August 1975 REGULATORY  
DIRECTORATE
GUIDE OFFICE OF STANDARDS  
OF REGULATORY  
DEVELOPMENT
STANDARDS REGULATORY  
REGULATORY  
GUIDE 1.16 REPORTING  
GUIDE 1.16 REPORTING  
OF OPERATING  
OF OPERATING  
INFORMATION-APPENDIX
INFORMATION
A TECHNICAL
Revision 1 October 1973 GUIDE
SPECIFICATIONS


==A. INTRODUCTION==
==A. INTRODUCTION==
of Reporting Requirements fo Pe u to NRC Regulations," and is not pre Section 50.36, "Technical Specifications," of 10 CFR Part 50, "Licensing of Production and Utilization B.  Facilities," requires that each applicant for a license authorizing operation of a nuclear power plant include In Septem b74 tomic Energy Commis in its application proposed technical specifications.
SCction 50.36. "TTechnical Specifications." of 10 CFR Part 50, "Licensing ot Production and Utilizationi Facilities," requires that easch applicant for a license authorizing operation of a nuclear power plant include in his applica tion proposed technical specifications.


sion 2 Re ory u hed Revision 2 of Regula These technical specifications, as issued by the NRC, are tory Guide ion reflected results of astaff incorporated into the facility license and are conditions review f information needed to permit of the license. Technical specifications are now included assess y Commission of safety-related activities as two appendices to the license: Appendix A technical " , erating phase of plant life. Significant specifications relate to health and safety, and Appendix ision 2 were: B technical specifications relate to environmental im- bporting requirements were updated to reflect pact.' Each of these appendices includes a section-l in reports required by Appendix A technical reporting requirements.
These technical specifications as approved by the AE-C are incorrporated into tire facility license and are conditions oif the license. The technical specifications for nuclear power plants include a section on reporting requirements.


The reporting program descril ci ications.
In addition to the reporting requirements necessary for compliance with the technical specifications of the license, there are specific reporting requirements included in Part 50 as well as in Parts 20.40. 70. and 73 of Title 10. For the convenience of licensees, these specific reporting requirements are included in the reporting program described in this guide. Each report discussed in this guide is either required by AEC regulations or is normally specified in licensees'
technical specifications.


In general, these changes involved:
In some cases this program may need to be supplemented or modified because of unique plant design features or other factors.The need for a supplemental or modified program will be determined on an individual-case basis. The Advisory Committee on Reactor S'feguards has heen consulted concerning this guide and has concurred in the regulatory position.
in this regulatory guide involves the reportin g /ul a. a change in frequency of submittal of ments of Appendix A technical specificatio oY. I routine operating reports; some cases, this program may need to be su emen* b. elimination of the first-year operating or modified because of unique plant design tarlr report; other factors. The need for a supplemental or ied c. formalization of reporting of operating program will be determined on a case-by-case basis. information on a monthly frequency;
Reporting of informati cerning radioactive d. deletion of certain items of information no discharges, radiological en monitoring, and longer required to be submitted on a routine basis; nonradiological environ nta er ce and environ- e. changes in the format and immediacy of mental impact is d' ,nn'lg atory Guide 4.8, reporting required for certain types of abnormal occur"Environmental Te Cal ci fcations for Nuclear rences (now called reportable occurrences);
and Power Plants."'
f. improved guidance concerning definitions In additi to ng requirements necessary and categories of significance of abnormal occurrences.


for compliance technical specifications, specific re- 2. Appendices were added to provide ttie desired porting requiren are included in Part 50, as well as format for radiation exposure reports and monthly in other Parts of 'i]tle 10, Chapter I, Code of Federal operating revorts.
==B. DISCUSSION==
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 following the startup of the facility.In addition to those reports that relate to the safety of operation of the plant, the information on nuclear materials safeguards that must be reported pursuant to the ('omliission's regulations is also included.


Regulations.
The AEI'Regulatory staff has ieviewed Ihe types sf inorloratislat needed. Based oln !tis review and a review irf licensees'
current reporting pt igrai.; the staff has developed guidelines fotr such repirtint..
Thik ituidc presents an acceptable reporting prourainn I ol powel reactor licensees.


A compilation of all reporting requirements
Ta hles I and II o1 this guide are coilpilaliotm.s of tinme limits or frequency
3. A listing of reports other than those required applicable to the various types of NRC licensees, includ- by Appendix A technical specifications was eliminated.
:inlervals
[tr subhnlitting routline and nonroutline report:,.  
Acceptable repoirtlin1 programs tor radioactive eflluents and environnmen.tal monitoring are presented in Regulatory Guides 1.21 (Safety Gtmide 211. "Measuring and Reporting oft'Effluents from Nuclear Pow\ver :lait<. and 4.1"'Measuring and Reportine ofi' R:idioct'livilt itl the Environs of Nuclear Power P1lhnts."'
respectively.


ing identification of the proper NRC addressee or ad (See Introduction above.) dressees and designation of the number of copies requir ed, is included in Regulatory Guide 10.1, "Compilation
Significant differences in Revision I of this guide from Regulatory Guide 1.16o formerly Safety Guide 16)dated October 27, 1971 are: I. Extensive quoting of the Commission*, regulations has been deleted. References to the appropriate portiots of the Commission's regulations are included itt Tables I and !1 of this guide.2. For ease of reference the reporting summary table included in the original guide has been divided into two tables (Routine Reports and Nonroutine Reports)3. Reporting requirements have been updated ti reflect changes in the Comnmission's regulations and the reports required by the technical specifications.
2 The Atomic Energy Commission was abolished by the Energy Reorganization Act of 1974, which also created the Nuclear 'A few facilities have a single appendix that contains the Regulatory Commission and gave it the licensing and related combined aspect of Appendices A and B. regulatory functions of the AEC.USNRC REGULATORY
GUIDES Comments should be sent to the Secretary of the Commission.


U.S. Nuclear Regulatory Commission.
4. Appendix A of this guide. "Standard iormtatl I't Reporting Abnorinal Occuirrences." ha,: h'etn added to give guidance to licensees suhmittinzg abnormal occurrence reports."Lines indicatc substantive chaivs O'wn10 plcvihitls issli


Washington, D.C. 20M.6 Attention:
====e. USAEC REGULATORY ====
Dockevting anld Regulatory Guides are issued to describe and make available to the public Service Section.
GUIDES Copies of published guides may be obtained by routs' ,ldicanig the divisions desired to the US. Atomic Energy Commission.


methods acceptable to the NRC staff of implementing specific parns of the Commission's regulations.
Washinglon.


to delineate techniques used by the staff in evalu- The guides are issued in the following ten broad divisions:  
D.C. 20545.pleguletory Guides are sisued to describe and make avr table to the public Attention:  
sting specific problems or postulated accidents, or to provide guidance to appi cents. Regulatory Guides era not substitutes for regulations, and compliance
Director of Regulatory Standards.
1. Power Reacters 4. Products with them is not required.


Methods and solutions different from those set out in 2. Research and Test Reactors 7. Transportation the guides will be acceptable if they provide a basis for the findings requisite to 3. Fuels and Materials Facilities
Comments and wu9grtiodls tfo methods acceptable to thP AEC Regulatory stalf ot Implementing
-. Occupational Health the issuance or continuance of a permit or license by the Commission.
&peailic paris of ImprOvements In these guides ere encourAged and shotrid be ient to the Secretary the Comtn4tion's regulations.


4. Environmental end Siting 9. Antitrust Review Comments snd suggestions for improvements in these guides are encouraged
to delineate technijuest used by the Staff in of the Commission, U.S. Atomic Energy Commission.
5. Materials and Plant Protection
10. General at all times. and guides will be revised, as appropriate, to accommodate com ments and to reflect new information or experience.


However. comments on Copies of published guides may be obtained by written request indicating the this guide. if received within about two months after its issuance, will be par- diviesions desired to the U.S. Nuclear Regulatory Commission.
W*%hinl.to.


Washington.
D.C. 20545.evaluating specific problems or potiulated accidents, or to provide guidance to Attention:
Chief. Public Proceedings Stafl.ipplicants.


D.C.  ticularly useful in evaluating the need for an early revision.
Regulatory Guides are not substitutes for regulations and compliance with them ih not required.


20M6. Attention:
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 6. Products the issuance or continuance of a permit or license by the Commission.
Director.


Office of Standards Development.
2. RePearch and Test Reactors 7. T samotatne 3. Fuels ant] Materials Facilities
8. Occuttationiri Hal h Published guides will be revised periodically, as a~ptopriate, to accommodalte
4, Envitonmntol and Siting 9. Ar-rtruit Rr.v,ewv commentS and to reflect new information or eaperience.


Comments were invited within 60 days of publica tion of Revision 2 for use in conjunction with early revision of the guide. As a result of comments received on the guide and additional staff review, the staff developed Revision 3. Significant changes in Revision 3 were: 1. The startup report was revised to be more specific as to the test results to be reported.
5. Materials and Plant Protection
 
10. Genetal ,, ,III ]11 II
2. The annual report section was revised to (1) further quantify the term "reduction in power," (2) provide further guidance on reporting of occupational radiation exposures, and (3) revise the information to be submitted on fuel performance.
* II I- ---  
 
C. REGULATORY
3. The abnormal occurrence report section was revised to (1) provide for prompt notification by telephone and confirmation of such notification by telegraph, mailgram, or facsimile transmission of the types of abnormal occurrences listed under Section 2.a, (2) be more specific on the types of abnormal occur rences reported, (3) delete radiological effluent releases from Appendix A technical specification reporting requirements, (4) provide for reporting of the types of abnormal occurrences listed under Section 2.b within 30 days of occurrence of the event, and (5) make Section 2.c of Revision 2 of the guide a separate section (Section 4).  In previous revisions of Regulatory Guide 1.16, the term "abnormal occurrence" was used to designate any unscheduled or unanticipated operational event reported to the Commission.
POSITION The following reporting program should be used to implement the reportintg requirements of 10 CFR Parts 20, 40. 50. 70. 73, and teporting requirenments imposed by the AEC as license conditions.
 
Included in these reported events were (1) events that could or did have significance from the standpoint of public health or safety and (2) events reported to NRC for performance evaluation and trend determinations.
 
In Section 208 of the Energy Reorgani zation Act of 1974 (Pub. L. 93438), an "abnormal occurrence" is defined for the purposes of the reporting requirements of the Act as an unscheduled incident or event which the Commission determines is significant from the standpoint of public health or safety. In order to be consistent with this definition, the events desig nated in previous revisions of this guide as "abnormal occurrences" are designated "reportable occurrences" in Revision 4. Any "reportable occurrences" that are determined by the Commission to be significant from the standpoint of public health or safety will be further designated "abnormal occurrences." C. REGULATORY
POSITION In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following program for reporting of operating information provides an acceptable basis to the NRC staff for meeting the reporting requirements of Appendix A technical specifi cations. Reports submitted in accordance with this guide should be addressed to the Director of the appropriate NRC Regional Office unless otherwise noted.  *Unes indicate substantive changes from previous issue.1. Routine Reports a. Startup Report.  A summary report of plant startup and power escalation testing should be submitted following
(1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.  The report should address each of the tests identified in the FSAR and should in general include a description of the measured valaes of the operating conditions or characteiistics obtained during the test program and a comparison of these values with design predictions and specifications.
 
Any corrective actions that were required to obtain satisfactory operation should also be de scribed. Additional specific details may be included in license conditions based on the applicant's commitment to applicable regulatory guides and should be included in this report.  Startup reports should be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or com mencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
 
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test pro gram, and resumption or commencement of commercial power operation), supplementary reports should be submitted at least every three months until all three events have been completed.
 
b. Annual Operating Report.3 Routine operating reports covering the opera tion of the unit during the previous calendar year should be submitted prior to March 1 of each year. The initial report should be submitted prior to March 1 of the year following initial criticality.
 
The primary purpose of annual operating reports is to permit annual evaluation by the NRC staff of operat ing and maintenance experience throughout the nuclear power industry.
 
The annual operating reports made by licensees should provide a comprehensive summary of the operating experierce gained during the year, even though some repetition of previously reported informa tion may be involved.
 
References in the annual operating report to previously submitted reports should be clear.  Each annual operating report should include: (1) A narrative summary of operating experi ence during the report period relating to safe operation of the facility, including safety-related maintenance not covered in item l.b.(2Xe)
below.  3 A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.1.16-2*
(2) For each outage or forced reduction in power 4 of over 20 percent of design power level where the reduction extends for more than four hours: (a) the proximate cause and the system and major component involved (if the outage or forced reduction in power involved equipment malfunction); (b) a brief discussion of (or reference to reports of) any reportable occurrences pertaining to the outage or power reduction;
.(c) corrective action taken to reduce the probability of recurrence, if appropriate; (d) operating time lost as a result of the outage or power reduction (for scheduled or forced out ages,s use the generator-off-line hours; for forced re ductions in power, use the approximate duration of op eration at reduced power); (e) a description of major safety-related corrective maintenance performed during the outage or power reduction, including the system and component involved and identification of the critical path activity dictating the length of the outage or power reduction;
and (f) a report of any single release of radio activity or single radiation exposure specifically associ ated with the outage which accounts for more than 10 percent of the allowable annual values. (3) A tabulation on an annual basis of the number of station, utility, and other personnel (in cluding contractors)
receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job functions, 6 e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe mainte nance), waste processing, and refueling.
 
The dose assign ments to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
 
Small exposures totalling less than 20 percent of the individual total dose need not be accounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
 
See Appendix A to this guide for a standard format for providing this information.
 
(4) Indications of failed fuel resulting from irradiated fuel examinations, including eddy current 4 The term "forced reduction in power" as used in this guide and as normally defined in the electric power industry means the occurrence of a component failure or other condition that requires that the load on the unit be reduced for corrective action immediately or up to and including the very next weekend. Note that routine preventive maintenance, surveillance, and calibration activities requiring power reductions are not covered by this section.
 
SThe term "forced outage" as used in this guide and as normally defined in the electric power industry means the occurrence of a component failure or other condition that requires 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 of 10 CFR Part 20.tests, ultrasonic tests, or visual examinations completed during the report period.  c. Monthly Operating Report.  Routine reports of operating statistics and shutdown experience should be submitted on a monthly basis. The report formats set forth in Appendices B, C, and D to this guide should be completed in accordance with the instructions provided.
 
The completed forms should be submitted by the tenth of the month following the calendar month covered by the report to the Director, Office of Management Information and Program Control, U.S. Nuclear Regulatory Commission, Waslitngton, D.C. 20555, with a copy to the appropriate NRC Regional Office.  2. Reportable Occurrences Guidance concerning reportable occurrences that should be reported in different time frames is provided below. Supplemental reports may be required to fully describe final resolution of the occurrence.
 
In cases of corrected or supplemental reports, a licensee event report should be completed and reference should be made to the original report date.  a. Prompt Notification With Written Followup.
 
The types of events listed below should be reported as expeditiously as possible, but within 24 hours by telephone and confirmed by telegraph, mail gram, or facsimile transmission to the Director of the appropriate NRC Regional Office, or his designee, no later than the first working day following the event, with a written followup report within two weeks. A copy of the confirmation and the written followup report should also be sent to the Director, Office of Managementj Information and Program Control, USNRC. The written followup report should include, as a minimum, a completed copy of the licensee event report form (see Appendix E to this guide) used for entering data into the NRC's computer-based file of information concerning licensee events. (Instructions for completing these licensee event report forms 7 are issued individually to each licensee.)
Information provided on the licensee event report form should be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.  (1) Failure of the reactor protection system or other systems subject to limiting safety-system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety-system setting in the technical specifi 7 Instruction Manual, Licensee Event Report File, Office of Management Information and Program Control, U.S. Nuclear Remglatory Commission, Washington, D.C. 20555.1.16-3 cations or failure to complete the required protective function.
 
The following are examples: 8 (a) Reactor pressure exceeds limiting safety-system setting value without automatic trip.  (b) Inability to trip and insert sufficient control rods to achieve the technical specification shut down margin.  (c) Failure of the reactor protective system to complete the required protective action once initi ated.  Note: Instrument drift discovered as a result of testing need not be reported under this item but may be report able under items 2.a(5),2.a(6), or 2.b(l) below.  (2) Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for opera tion established in the technical specifications.
 
The fol lowing are examples: (a) Shutdown not begun within the speci fied time when unidentified reactor coolant leakage ex ceeds the technical specifications limit.  (b) Failure of a system other than the systems subject to limiting safety-system settings (see 2.a(l) above) to actuate, or actuation of such a system at a monitored parameter value less conservative than that listed in the technical specifications for the system.  (c) Operation with unacceptable contain ment leak rate type B or C test results.  (d) System cooldown at a rate exceeding the technical specifications limit.  Note: If specified action is taken when a system is found to be operating between the most conservative and the least conservative aspects of a limiting condition for operation listed in the technical specifications, the limiting condition for operation is not considered to have been violated and need not be reported under this item, but it may be reportable under item 2.b(2) below.  (3) Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.
 
The following are examples: (a) Through-wall failure of piping or com ponents of the reactor coolant pressure boundary.  (b) Steam generator tube thinning in excess of acceptance limits in Regulatory Guide 1.83, "Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes." (c) Welding or material defects greater than those allowable by applicable codes.  Note: Leakage of valve packing or gaskets within the limits for identified leakage set forth in technical specifi cations need not be reported under this item.  8Examples are intended to be illustrative only.(4) Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady-state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a shutdown margin less conservative than specified in the technical specifications;
short-term react ivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% Ak/k; or occurrence of any unplanned criticality.
 
S(5) Failure or malfunction of one or more com ponents which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s)
used to cope with accidents analyzed in the SAR. The following are examples: (a) Clogged fuel line(s) resulting in failure to supply fuel to the emergency generators.  (b) Multiple instrument drift resulting in loss of protective function.  (c) HPCI failure to start or failure to con tinue running once initiated.
 
(6) Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfill ment of the functional requirements of systems required to cope with accidents analyzed in the SAR. The follow ing are examples: (a) Failure to restore a safety system to operability following test or maintenance.  (b) Improper procedure leading to in correct valve lineup which resulted in closure of one manual valve in each of two redundant safety injection subsystems and would have prevented injection on demand.  Note: For items 2.a(5) and 2.a(6) reduced redundancy that does not result in loss of system function need not be reported under this section but may be reportable under items 2.b(2) and 2.b(3) below.  (7) Conditions arising from natural or man made events that, as a direct result of the event, require plant shutdown, operation of safety systems, or other protective measures required by technical-specifications.
 
The following are examples: (a) Threatened civil disturbances requiring plant shutdown.  (b) Damage to the facility caused by fire, flood, earthquake, or other similar occurrences.
 
(8) Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
 
The following are examples: (a) Loss of condenser vacuum resulting in reactor pressure and flux transients that peak at values higher than analyzed.1.16-4 (b) Reactivity insertion delay times by reactor protection system longer than those used in the technical specification bases.  (9) Performance of structures, systems, or com ponents that requires remedial action or corrective measures to prevent operation in a manner less conserva tive than that assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical spe cifications that require remedial action or corrective measures to prevent the existence or development of an.  unsafe condition.
 
The following are examples: (a) Axial flux ratios less conservative than those for which correlations with overpower AT were based on core bumup projections.  (b) Failure of a safety injection pump to deliver the flow rates assumed in the FSAR.  (c) Degradation of hydraulic shock sup pressors to the extent that they could not perform their required safety function.  (d) Failure of magnetic trip mechanisms on a safety-related circuit breaker to provide trip on instantaneous overcurrent as indicated on the manufac turer's time-current characteristic curve.  (e) Failure of a safety/relief valve to close after pressure has reduced below the required reseat valve.  (f) Thermal shock to the reactor coolant system resulting from inadvertent safety injection actua tion.  Note: This item is intended to provide for reporting of potentially generic problems.
 
b. Thirty-Day Written Reports.
 
The reportable occurrences discussed below should be the subject of written reports to the Director of the appropriate NRC Regional Office within 30 days of occurrence of the event. A copy of the written report I should also be sent to the Director, Office of Manage ment Information and Program Control. The written report should include, as a minimum, a completed copy of the licensee event report form (see Appendix E to this guide) used for entering data into the NRC's computer-based file of information concerning licensee events. (Instructions for completing these licensee event report forms 7 are issued individually to each licensee.)
Information provided on the licensee event report form should be supplemented, as needed, by additional narra tive material to provide complete explanation of the cir cumstances surrounding the event.  (1) Reactor protection system or engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems. The following are examples: (a) One of the four scram dump volume level switches failed to operate during surveillance test.  (b) One of four reactor low-pressure switches operated at 885 psig instead of LSSS value of 900 psig.  (c) During test, one out of four under voltage relays failed to perform its function of tripping a reactor trip breaker.
 
"(2) Conditions leading to operation in a de graded mode permitted by a limiting condition for operation, or plant shutdown required by a limiting condition for operation.
 
The following are examples: (a) Core spray pump breaker tripped after 20 minutes during test. Trip unit was found to be defective, declared inoperable, and repaired.  (b) Safety injection pump failed to start following system initiation.


Required surveillance on redundant components was successfully completed.  (c) One of the two centrifugal charging pumps became inoperable because of a faulty bearing.
including those reports required by thie tclnlical specilrCations.


Redundant pump operability was confirmed.
1. Routine Reports a. Operations Reports'I I ) Startup Report. A summary. report of plant startot) and power escalation testing should he submittcd I'o0lowitrg reccipi t it' ai upctatintg license, tollowing an amendment it the licenise involving -a planned increase in power level. ft,..owin iv the iLnstall.'tinn of rrel il has if different design ur hlas been nranuutfactrrred by a different fuel supplier.


Note: Routine surveillance testing, instrument calibra tion, or preventive maintenance which require system configurations as described in items 2.b(l) and 2.b(2) need not be reported except where test results them selves reveal a degraded mode as described above. (3) Observed inadequacies in the implementa tion of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems. The following are examples: (a) One of the three diesel generators tripped from high temperature because cooling water valves were lined up incorrectly.  (b) Isolation valve for a low-pressure trip switch was found closed with system pressure locked in.  Trip of switch would not occur at low pressure.
or fIOllowing modi fications dial nay haive signifilcantly ahlrred the nuclear. thermal. or hydranlic perftorniance iI" Ithe pl:ant. The report should include a description of The
';iltiues tit' the ocerating conditions or ctharacteristics obtained during the test progratn and a comnparison of these values with design predictions and specifications.


Improper return to operation following maintenance was the cause. (c) Failure to perform surveillance tests at the required frequency.
Any corrective actions that Were requ.ired to obtain sattisfactlotv operarior should also he' dcr itwcd. Sr rtrup reporls sluimld lie slrblnlilrled willitm I1) 10 clays following cormpletion of Ire stalt tip test ptoi gra in. (2) 90 days following resturnpli cr rit ior c ntten nt o1f c rommerciaI
po'wer operation.


(4) Abnormal degradation of systems other than those specified'in item 2.a(3) above designed to contain radioactive material resulting from the fission process. For example, a through-wall leak in a liquid waste storage tank.  Note: Sealed sources or calibration sources are not included under this item. Leakage of valve packing or gaskets within the limits for identified leakage set forth in technical specifications need not be reported under this item.1.16-5
or 31 t ) nronths following initial criticality.
3. Unique Reporting Requirements The above reporting program will in general satisfy the reporting requirements necessary for compliance with Appendix A technical specifications.


This program may need to be supplemented or modified because of unique plant design features or other factors. The need for a supplemental or modified program will be deter mined on a case-by-case basis and so designated in individual operating licenses.
whichever is earliest.


4. Events of Potential Public Interest The types of events listed below are frequently of high public interest.
If thie Startutp Report does not cover all tihrec cverrts. i.. initiial criticalily.


While some of the events may not be reportable by regulation or defined in other parts of this guide, the Director of the appropriate NRC Regional Office, or his designee, should be informed of such events by telephone as soon as possible after the event has been discovered.
cotmlpletion ot S :c rl tip t st C plro ra iii. rod resl rillpt loll or ce to nmterncete.


a. An event that causes damage to property or equipment when such damage affects the power pro duction capability of the facility.
of :o Inetrrc ial poe'r operatiion.


b. Radiation exposure to licensee personnel or members of the public in excess of applicable exposure limits set forth in 10 CFR Part 20. c. Natural or man-made conditions that may require action which need not be reported under item 2.a(7) above.  d. Discovery of significant radiological event off site occurring during transport of material for which the licensee was either shipper or consignee.
Suplplementa'ry rep.crts Slhou.ld he srtbitritted at least every lthrce trit ;i ll! hi c evonts are t.orrpleted.


e. Unscheduled shutdowns expected to last for more than one week, regardless of cause.  f. Unusual releases of radioactive material from the site boundary not reportable under other require ments. g. Failure of or damage to safety-related equip ment which need not be reported under item 2.a above, if the time for repair is likely to exceed the time allowed by the technical specifications.
(2) First Year Operaton Report. A report sh1trld hC subnrittled wit hin 60 days aftier completion of the first year oit operalion.


==D. IMPLEMENTATION==
This .tar begi ms oc coltplet ion tt'o all three evetlt s listed in C.;.a.i i ). This report mtay he incorpor:ated into tile semiatrtrtl olperatrino relport rard shurld cover tire following:
The purpose of this section is to provide informa tion to applicants and licensees regarding the NRC staff's plans for utilizing this regulatory guide. Except in those cases in which the applicant proposes an acceptable alternative method, the reporting program described herein is being used by the NRC staff in order to standardize the reporting requirements section of Appendix A technical specifications of all operating licenses.
(:ill ;m ,n v:ltr;!tit1In
'; plhrtl ltcc hi dale in corinlprisim wi! Ii 'sicti !tiedicticlns and S1 O: ilic.l iI jihltilsl' ,ilil subriitied Witlh the license application i1" measured operating characteristics indicate that there may be substantiialvariance fronm prior analyses:2 (c) an assessrenrt of file performance of strtctures.


For licensees holding operating licenses without Appendix B environmental technical specifications, it may be necessary to include those reports identified in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," and Regulatory Guide 4.1, "Programs for Monitoring Radio activity in the Environs of Nuclear Power Plants," in the technical specifications under the unique reporting requirements section of the technical specifications.
sysletrs.


1.16-6 APPENDIX A STANDARD FORMAT FOR REPORTING
and components iml'-rtant to safety: thill iti, Ca, L !,. l. .1titihctcld bhe S.tllrith:
NUMBER OF PERSONNEL
ill writirg tI0 Ie I)reclror or r th I e ;Ipprlrltialte AViC Re utailort -(i,,cration n Regionial Office.2I'rciously r it rit tedl sal % ;! raysi.s repo r r i V.inLccrloritlcl hb t eretilrce.(d) a progress and status report oir airy items identified as requiring additional inforitation during tire operating license review or during the startup of tlie facility, including ilemns discussed in tile AEC's Safely Evaluation Repmrt and Supplements, items on which additional information was required as a conrdition of the license. and itemrs identified in the licensee's st:artup report: and (e) a report of measured in-plant radiation levels which are greater thiran those estimated irr the final safety analysis report by a factor of two or more.(3) Semiannual Operating Reports? Routine operating reports covering tire operation o tIrh pre2 us h (I mionths should be subtrmitted witiirt 60 days after Jartnuary I and Jtly I of each year. The initial report shtitld he stthlirited Withint 00 days after the cild iI' the first six-nmonth period during which initial criricalily took place. Fa ch report should inelnrde the followirrg: (a) Operations Sumrnmar'.  
AND*MAN-REM
A stinrirary of operating experience occurring during the reportiog period that relates to tire s:icu operation of the facility.including a sumnmary of: (i) changes in facility design.(it) performance characteristics (e.g..eqttipreti t ;tnid fuel per formlance), (iii) changes in) operating procedutres which were necessitated by (i) and (ii) above or which otherwise were required to improve thie saklty of operations, (iv) results of surveillance tests and inspections required by the licensee's technical speciftications.(v) the results of aniy periodic cottainment leak rate tests performed during the reporting period.(vi) a brief suimmary of tirosk cihtanges.
BY WORK AND JOB FUNCTION Number of Personnel
(> 100 nurem) Total Man-Remn Contract Workers Contract Workers Work & Job Function Station Employees Utility Employees and Others Station Employees 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 Special Maintenance Maintenance Personnel Operating Personnel Health Physics 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 GrandJ XULM I IJ I .I"1 _ ..1 "IP^+^I
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. UNIT DATE COMPLETED
BY TELEPHONE MONTH DAY AVERAGE DAILY POWER LEVEL (MWe-Net)  
1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)  
17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 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.


These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used 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 power output sheet should be footnoted to explain the apparent anomaly.
tests. and experiments requiring auLthorization from the Commission purtntant to 10 CMR 50.59(a), and (vii) any chanrges in thie p1lnt operating staff for thiose positions designated as key stipervisory personniel positions in the technical specificairs.(b)powet generated Power Generation.


1.16-8 APPENDIX C OPERATING
A sumnnmary of during the reporting period including: (iM gross thermal power geterated (itn MWI 1).(ii) gross electrical power generated (in MWH), (iii) number of iours tire reactor was critica!, (iv) number of hours the generator was on line, and (v) histogram of thermal power vs.t if e.'A sinrde subliimr itl may be imadrde for a multiple facility mat iim. The stticrrthittal shiould corritine tinrow. eclions Irh are comllrrrlrn iI all I'acilitics at ilre station.I .I0c-2 I *(c) Shutdowns.
DATA REPORT DOCKET NO. UNIT DATE COMPLETED
BY TELEPHONE
OPERATING
STATUS


===1. REPORTING ===
Descriptive material covering all outages occurring during the reporting period. For each outage, information should be provided oil: (i) tile cause of the outage, (ii) the inethud of shutting down the]reactor;
PERIOD: GROSS HOURS IN REPORTING
e.g.. trip, automatic rundown, or manually controlled deliberate shutdown'(iii) duration of the outage (in hours), (iv) plant status during the outage'e.g.. cold shutdown or hot standby, and (v) corrective action taken to prevent repetition, if appropriate.(d) Maintenance.
PERIOD:


===2. CURRENTLY ===
A discussion of corrective maintenance (excluding preventive maintenance)  
AUTHORIZED
performed during the reporting period on safety-related systems and components4 and on systems and components that reduce or prevent the release of radioactive materials to the environs.
POWER LEVEL (MWt): ._ MAX. DEPEND. CAPACITY (MWO-Net):
DESIGN ELECTRICAL
RATING (MWe-Net):
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):
4. REASONS FOR RESTRICTION (IF ANY): THIS MONTH 5. NUMBER OF HOURS REACTOR WAS CRITICAL................ 
6. REACTOR RESERVE SHUTDOWN HOURS....................


===7. HOURS GENERATOR ===
For any malfunction for which corrective maintenance was required, information should be provided on: (i) t he system or component involved, (ii) the cause of the malfunction.(iii) the results and effect on saf.operation.
ON LINE ...... .................... 
8. UNIT RESERVE SHUTDOWN HOURS. ...................... 
9. GROSS THERMAL ENERGY GENERATED (MWH)............... 
1


===0. GROSS ELECTRICAL ===
and (iv) corrective action taken to prevent repetition.(e) Changes, Tests and Experiments.
ENERGY GENERATED (MWH).............. 
1


===1. NET ELECTRICAL ===
A brief description and the summary of the safety evaluation for those changes, tests, and experiments, carried out without prior Commission approval pursuant to the provisions of IOCFR 50.59(b).(f) Primary Coolant Chemistry.
ENERGY GENERATED (MWH)............... 
12. REACTOR SERVICE FACTOR. ........................... 
13. REACTOR AVAILABILITY
FACTOR........................ 
14. UNIT SERVICE FACTOR .............................. 
1


===5. UNIT AVAILABILITY ===
A tabulation on a monthly basis of the maximum. average, and minimum values for the following primary coolant system parameters: (i) Gross radioactivity in pCi/ml.(ii) Suspended solids in parts per million.(iii) Gross tritium in pCi/ml.(iv) Iodine 131 in pCi/ml, (v) Ratio of Iodine-131 to Iodine-I133.(vi) Hydrogen in cc per kg.(vii) Lithium in parts per million.(viii) Boron-lO in parts per million.(ix) Oxygen-16 in parts per billion, (x) Chloride in parts per million, and (xi) pH at 25 0 C.4Those plant features necessary to assure the integrity of the reactor coolant pressure boundary.
FACTOR .... ...................... 
16. UNIT CAPACITY FACTOR (Using MDC). ..................... 
17. UNIT CAPACITY FACTOR (Using Design MWel..................
YR TO DATE CUMULATIVE
18. UNIT FORCED OUTAGE RATE .........................................
1


===9. SHUTDOWNS ===
the capability to shut down the reactor and maintain it in a jal'vo shtdown condition.
SCHEDULED
OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): 20.  21.IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED
DATE OF STARTUP: UNITS IN TEST STATUS (PRIOR TO COMMERCIAL
OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY
INITIAL ELECTRICITY
COMMERCIAL
OPERATION 1.16-9 I I I
INSTRUCTIONS
FOR COMPLETING
OPERATING
DATA REPORT This report should be furnished each month by licensees.


The name and telephone number of the preparer should be provided in the designated spaces. The instructions below are provided to assist licensees in reporting the data consistently.
or the capability to prevent or miti~oc tite consequences of1 accidents which could result in o''.itc e,'i.sures comparable to the guideline exposures of 10 CFR Part 100.(g) Occupational Personnel Radiation Exposure i) A tabulation of 0i1e titinher Of occupational personnel exposures for plan' operations personnel (permanent and temporary)
in the following exposure increments for the reporting period: less thatn 100 mrerm, 100-250 ortem. 250-500 ntoem. 5001-750 morem, 750-1000 mrem. 1-2 rem. 2.3 retn. 3.4 rem. 4-S rem, 5.6 rem, and greater than 6 remi.(ii) A tabulation of the nurniter ot'personnel receiving more than 500 mrem exposure in the reporting period according to duty function le.g..routine plant surveillance and inspection (regular duty), routine plant maintenance, special plant mainten:itce (describe maintenance).
routine fueling operation.


The number of the instruction corresponds to the item number of the report form. 1. Reporting Period. Designate the month for which the data are presented.
special refueling
(,peration (describe and other job-related exposures.](iii) A tabulation annually of the number of personnel receiving more than 3 rein atnd fie major cause(s).(hi) FSAR Changes. Submission of revised FSAR pages on a replacement page basis appropriately r7epared for direct insertion into the applicable FSAIR section and describing all safety.related chaniges in'facility design. method of operation.


The Gross Hours are normally from 0001 of the first day through 2400 of the last day of the calendar month, with appropriate adjustments for any month in which a change from standard to daylight-saving time (or vice versa) is made. The only two shorter reporting periods are (1) the one in which the initial electrical generation occurs and (2) the one in which the reactor is shut down for decommissioning.
revised safety or transient analysis.


In the former, the gross hours, expressed to the nearest tenth of an hour, are those from the time of initial power generation to 2400 of the last day of the calendar month. In the latter case, the gross hours, expressed to the nearest tenth of an hour, are those from 0001 of the calendar month to the specific time of final shutdown.
or f:,cility equipment additiots.


2. The Authorized Power Level is the maximum thermal power, expressed in megawatts, currently authorized by the Nuclear Regulatory Commission.
Also a listing of effective pages by date of revision or revisiotn number should be submitted.


The net Maximum Dependable Capacity is the gross electrical output as measured at the output terminals of the turbine-generator during the most restrictive seasonal conditions less the normal station service loads. The net Design Electrical Rating is the nominal net electrical output of the unit specified by the utility and used for the purpose of plant design.  3. Note that this item is applicable only if restric tions on the power level are in effect. Short-term (less than one month) limitations on power level need not be presented in this item, since one of the important purposes of the item is to determine if, and at what power level, a restricted power level line should be drawn on the chart of average daily reactor power.  Since this information is used to develop figures on capacity lost due to restrictions and because most users of the "Operating Plant Status Report" are primarily interested in energy actually fed to the distribution system, it is requested that this figure be expressed in MWe-Net in spite of the fact that the figure must be derived from MWt or percent power.  4. Reasons for Restriction (if Any). If item 3 is used, item 4 explains why. Brief narrative is acceptable.
b. Additional Routine Reporting Requirements.


Cite references as appropriate.
Table 1 lists routine reports required by 10 CFR Parts 20. 40, 50. and 70. including those listed in Regulatory Position C.I .a.2. Nonroutine Reports a. Reporting of Abnormal Events (1) Abnormal Occurrence Reports. A notification must be made within 24 hours by telephone and telegraph to the Director of the appropriate AlFC Regulatory Operations Regional Office. (cc to the Director of Licensing)
followed by a written report wihrin 10 days to the Director of the appropriate AlEC Regulatory Operations Regional Office in the event of an abnormal occurrence.


Indicate whether restric tions are self-imposed or are regulatory requirements.
Appendix A of this guide, "Standaid Format for Reporting Abnormal Occurrences.-  
should be used as guidance when submitting abnotmtal occurrence reports.Abnormal occurrences are defined in the definitions section of the licensee's technical specifications and usually include, as a miniutitll, items (a) through (h) of this paragraph.


Be as specific as possible within space limitations.
1 1 -3 (a) A safety. systeil setting- :ess conlservative titan the limiting setting, established in the technical specifications.(b) Conditions which result in a limiting condition for operations established in the technical specilfications not being met.'0 Abnormal degradation of one of thie several boundaries designed to contain radioactive materials.(d) An unplanned or uncontiolled release of radioactive material from the site boundary.(e) Uncontrolled or unanticipated changes in reactivity "qual to or greater than 1% Akikk.(') Incidents or conditions which prevented or could have prevented the performance of thle intended safely function of an engineered safely feature system or of the reactor protection system.(g) Observed inadequacies in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connection with tile opelation of the plant.(h) Conditions arising from natural of man-made events that affect or threaten to affect the sale operation of the plant.(2) Reporting of Unusual Events. A written report should be forwarded within 30 days to the Director of t(ie appropriate AEC Regulatory Operations Regional Office, in the event of: (a) Discovery of any substantial errors in the transient or accident analyses, or in the methods used for such aitalyses.


Plants in startup and power ascension test phase should be identified here.  5. Show the total number of hours the reactor was critical during the gross hours of the reporting period. 6. Reactor Reserve Shutdown Hours. The total number of hours during the gross hours of reporting period that the reactor was removed from service for administrative or other reasons but was available for operation.
as described in the Safety Analysis Report or in the bases for the technical specificat ions.(b) Discovery of any substantial variance from performance specifications contained in the technical specifications or in thle Safety Analysis Report.(c) Discovery of any condition involving a ipossible single failure which. for a system intended to be designed against assumed single failures.


7. Hours Generator On Line. Also called Service Hours. The total number of hours during the gross hours of the reporting period that the unit operated with breakers closed to the station bus. These hours, plus those listed in Appendix D for the generator outage hours, should equal the gross hours in the reporting period. 8. Unit Reserve Shutdown Hours. The total number of hours during the gross hours of the reporting period that the unit was removed from service for economic or similar reasons but was available for operation.
could result in a loss of the capability Of the system to perform its safety'loun ion.b. Additional Nonroutine Reporting Requirements Table II lists nonroutine reports required by 10 CFR Parts 20. 40, 50, 70, and 73. including those listed in Regulatory Position C.2.a.i 5A~ defined in 10CF]R 50.36(c).1.16-4
0e Requirement T'SI TS TS&sect;20.407&sect;20.408&sect;40.64(a)&sect;40.64(a)&sect;40.64(b)&sect;50.59(b)&sect;70.53&sect;70.54&sect;70.54 Appendix G to 10 CFR Part 50 Appendix H to 10 CFR Part 50 Appendix J to 10 CFR Part 50 Startup First Year (Semiannual Personnel E Personnel E Employmen Transfer of Receipt of , Source Mate Changes, Te Special Nuc.Transfer of Receipt ofS Fracture To TA8LE I REPORTING
SUMMARY-ROUTINE
REPORTS*Report Timing of Submittal 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.


9. Gross Thermal Energy Generated.
whiiclhever is earhest.If all thrce events arc not completed.


The thermal output of the nuclear steam supply system during the gross hours of the reporting period, expressed in megawatt hours.  10. Gross Electrical Energy Generated.
supplementairy reports every 3 monu~ths.)perat.on Within 60 days after completion of the first yeat of operation.


The electrical output of the unit measured at the output terminals of the turbine-generator during the gross hours of the reporting period, expressed in megawatt hours.  11. Net Electrical Energy Generated.
Within 60 days after January Iand July I of each year.xposure and Monitoring Within first quarter of each calendar year.xposure on Termination of Within 30 days after the exposure of the individual has it or Work been determined or 90 days after date of termination of employment or work assignment.


The gross elec trical output of the unit measured at the output terminals of the turbine-generator minus the normal station service loads during the gross hours of the reporting period, expressed in megawatt hours. Negative quantities should not be used. If there is no net positive value for the period, enter zero. 12-18. For units still in the startup and power ascension test phase, items 12-18 should not be com puted. Instead, enter N/A in the current month column. These seven factors should be computed starting at the time the unit is declared to be in commercial operation.
whichever is earlier.Source Material Promptly upon transfer.ource Material Within 10 days after material is received.erial Inventory Within 30 days after June 30 of each year.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 year.Special Nuclear Material Promptly upon transfer.Special Nuclear Material Within IK days after material is received.ughness On an individual-case basis at least 3 years prior to the 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.ssel Material Surveillance Completion of tests after each capsule withdrawal.


The cumulative figures in the second and third columns should be based on commercial operation as a starting date. However, units already in commercial operation, for which cumulative figures have been based on different starting dates, need not recalculate the cumula tive figures.1.16-11
ntainment Building Approximately
12. Reactor Service Factor. Compute by dividing hours reactor was critical (item 5) by the gross hours in the reporting period (item 1). Express as percent to the nearest tenth of a percent. During months when the unit is shut down for the entire period because of nonreactor problems, enter "Not Applicable" and explain in the Summary of Appendix D. Do not include reserve shutdown hours in the calculation.
3 months following conduct of test..eak Rate Test Reactor Ve Reactor Con Integrated L ITechnical Specifications
1.16-S
A 4 ..TABLE II REPORTING
SUMMARY-NON
ROUTINE REPORTS Initial Writtan Report Within 10 days 15 days 30 days 3 mo Requirement Report Notification T'I TS Abnormal Occurrence Unusual Events Within 24 hours X&sect;20.405&sect;20.402 Overexposures and Excessive Levels of Radiation and Concentration of Radioactive Material X X X Theft or Loss of Material Immediately
&sect;20.403(a)
Severe Accident lnvolhiir Licensed Material&sect;20.403(b)  
Accident Involving Licensed Material Imnediately Within 24 hours&sect;40.64(c)&sect; 50.59(d)&sect; 70.52&sect; 73.42 Theft or Unlawful Diversion of Source Material Authorization of Cl, "cs,.and Experiments Accidential Criticality or Loss of Special Nuclear Material Unaccounted for Shipments.


13. Reactor Availability Factor. Compute by divid ing the reactor available hours (items 5 plus 6) by the gross hours in the reporting period (item 1). Express as percent to the nearest tenth of a percent.
Suspected Theft. or Unlawful Diversion of Special Nuclear Material Prompt ly X IP'rotmplvl I tmnmediately X TS Special V.'Technical Specifications.


14. Unit Service Factor. Compute by dividing hours the generator was on line (item 7) by the gross hours in the reporting period (item 1). Express as percent to the nearest tenth of a percent. Do not include reserve shutdown hours in the calculation.
AEC authorization is required prior u) perfokrniinc a chune. tcsi. ,r e\perime1nt in tlis L.lteyorV.


15. Unit Availability Factor. Compute by dividing the unit available hours (item 7 plus item 8) by the gross hours in the reporting period (item 1). Express as percent to the nearest tenth of a percent.
3 Special reports covering inspections, tests. and maintenance that are appropriate to assure safe operaliol of'i lt fIcliliry.


16. Unit Capacity Factor (Using MDC). Compute by dividing net electrical energy generated (item 11) by the product of maximum dependable capacity (item 2) times the gross hours in the reporting period (item 1). Express as percent to the nearest tenth of a percent.
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.


17. Unit Capacity Factor (Using Design Electrical Rating). Compute as in item 16, substituting design electrical rating for maximum dependable capacity.18. Unit Forced Outage Rate. Compute by dividing the total forced outage hours (from the table in Appendix D) by the sum of hours generator on line (item 7) plus total forced outage hours (from the table in Appendix D). Express as percent to the nearest tenth of a percent.
Such reports include inservice inspection.


19. Shutdowns Scheduled to Begin in Next 6 Months. Include type (refueling, maintenance, other), proposed date of start of shutdown, and proposed length of shutdown.
tendon sunreillance procrani study, fuel inspection.


It is recognized that shutdowns may be scheduled between reports and that this item may not be all inclusive.
and contanirnment ur:l :c'.ls.I .16-6 A 9 t.-a 0 APPENDIX A STANDARD FORMAT FOR REPORTING
ABNORMAL OCCURRENCES
The standard format for submission of abnormal occurrence reports (AOR) identifies the principal information that should be contained in a completed AOR and gives a' format for presenting it. In the course of reviewing past AOR's the AEC Regulatory staff has found a wide variance in the type and detail of information reported.


Be as accurate as possible as of the date the report is prepared.
To assure that AOR's submitted are consistent both in format and in the principal information included, the format for abnormal occurrence reports presented below should he usci and the information requested should be submitted when applicable.


20. Self-explanatory.
If investigation is not complete by the time the initial report is submitted, the licensee should so indicate and give estimated time when a supplemental report will be submitted.


21. Self-explanatory.
STANDARD FORMAT FOR ABNORMAL OCCURRENCE
REPORTS Report Number: .(1)Report Date: (2a)Occurrence Date: (2b)Facility:
(3)Identification of OccUrrence:
(4)Description of Occurrence:
(6)Designation of Apparent Cause of Occurrence:
(7)Design Manufacture Installation/Construction-Operator-Procedure-Unusual Service Condition Including Environmental-Component Failure-Other (specify)Analysis of Occurrence:
(8)Corrective Action: (9)Failure Data: (10)Conditions Prior to Occurrence:
(5)-Steady-State Power-Hot Standby-Cold Shutdown-Refueling Shutdown-Routine Startup Operation-Routine Shutdown Operation Load Changes During Routine Power Operation-Other (Specify)NOTES TO AOR STANDARD FORMAT I. Report Number: Abnormal occurrence reports should be numbered sequentially on a calendar-year basis for each facility (or each unit of a multi-unit site) using the facility (unit) docket number as the principal identifier (e.g., Docket NumberJYear-Sequential Number in calendar year).Supplementary reports should be numbered using alphabetical identifying letters following the principal report number (e.g., Docket Number/Year-Sequential Number in calendar year-alphabetical letter identifying supplementary report.)2. Report Date: Date occurrence.


Note, however, that this infor mation is requested for all units in startup and power ascension test status and is not required for units already in commercial operation.
of (a) report submitted and (b)3. Facility:
Name and location of facility.4. Identification of Occurrence:
The abnotmal occurrence should be identified by a short title'which identifies the type of abnormal occurrence and the system, component.


Test Status is defined as that period following initial criticality during which the unit is tested at successively higher outputs, culminating with operation at full power for a sustained period and completion of warranty runs. Following this phase, the unit is generally considered by the utility to be available for commercial operation.
or even, involved.(Regulatory Position C.2.a.(I)
should be used as a guide for listing the type of abnorml occurrence.)
1.16-7 a S. Conditions Prior to Occurrence:
Thie applicable c:apf ion should be used followed by a description of plant status prior to tie abnormal occurrence.


Date of Commercial Operation is defined as the date that the unit was declared by the utility owner to be available for the regular production of electricity, usually related to the satisfactory completion of qualifi cation tests as specified in the purchase contract and to the accounting policies and practices of the utility.1.16-12 APPENDIX D DOCKET NO.  UNIT SHUTDOWNS
Major plant parameters should be included.6. Description of Occurrence:  
AND POWER REDUCTIONS
A chronological sequence of events should be described in an objective manner. The following should be included: a. Method of detection and time of detection.
UNIT NAME DATE COMPLETED
BY REPORT MONTH TELEPHONE METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR NO. DATE S: SCHEDULED (HOURS) REASON (1) REDUCING POWER (2)- CORRECTIVE
ACTIONS/COMMENTS
(1) REASON A: EQUIPMENT
FAILURE (EXPLAIN)
B: MAINT. OR TEST C: REFUELING
D: REGULATORY
RESTRICTION
E: OPERATOR.TRAINING
AND LICENSE EXAMINATION
F: ADMINISTRATIVE
G: OPERATIONAL
ERROR (EXPLAIN)
H: OTHER (EXPLAIN)
(2) METHOD 1: MANUAL 2: MANUAL SCRAM 3: AUTOMATIC
SCRAM 4: OTHER (EXPLAIN)SUMMARY:
UNIT SHUTDOWNS
AND POWER REDUCTIONS
INSTRUCTIONS
This report should describe all plant shutdowns dur ing the report period. In addition, it should be the source of explanation of significant dips in average power levels (Appendix B). Each significant reduction in power level (greater than 20% reduction in average daily power level for the preceding
24 hours) should be noted, even though the unit may not have been shut down completely)
For such reductions in powe+/- lew', the duration should be listed as zero, the method of reduc tion should be listed as 4 (Other), and the Comments column should explain. The Comments column should be used to provide any needed explanation not ade quately described by the coded columns. Please do not add to the list of codes or legends now furnished.


Simi larly, do not add additional columns.
b. Step-by.step sequoence of events identif'ying all protection system :tctions and operator actions to hrmig fhc sitation under control.7. Designation of Apparent Cause of Occurrence:
The single apparent cause should be identified and narrated.


Number. This column should indicate the sequential number assigned to each shutdown or significant reduc tion in power for that calendar year. When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or signifi cant power reductions are reported.
When other causes contributed to the abnormal occurrence.


Until a unit has achieved its first power generation, no number should be assigned to each entry. Date. This column should indicate the date of the start of each shutdown or significant power reduction.
the narrative of the apparent cause should discuss fully the single cause assigned and the contributing causes assigned.8. Analysis of Occurrence:
The abnormal occurrence should be analyzed for safety implications.


Report as year, month, and day. August 14, 1975 would be reported as 750814. When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.
The analysis of effect." and the attendant consequences should include tile following information, as applicable:
a. Maximum and ,minimum conditions during transients.


Type. Use "F" or "S" to indicate either "Forced" or "Scheduled," respectively, for each shutdown or signifi cant power reduction.
b. Equipment malfunction.


Forced shutdowns include those 'Note that this differs from the Edison Electric Institute (EEl) definitions of "Forced Partial Outage" and "Scheduled Partial Outage." For these terms, EEl uses a change of 30 MW as the break point. For larger power reactors, 30 MW is too small a change to warrant explanation.
c. Operator error.d. Damage to systems. components.


required to be initiated by no later than the weekend following discovery of an off-normal condition.
and structures.


It is recognized that some judgment is required in categori zing shutdowns in this way. In general, a forced shut down is one that would not have been completed in the absence of the condition for which corrective action was taken. Duration.
e. Personnel injuries.f. Personnel exposures.


Self explanatory.
g. Quinmtity and composition of radioactive materials released.Ih. The consequences cr potential colsequnclies
&#xfd;from the standpoint of public healfli and safety.9. Corrective Action:' The following informalion should he provided: a. Correclive action lakcn (or to he laken) to correct tile abnormal occurrence.


When a shutdown extends beyond the end of a report period, count only the time to the end of the report period and pick up the ensuing down time in the following report periods. Report dura tion of outages rounded to the nearest tenth of an hour to facilitate summation.
It. Corrective action taketn (or to he i;keinL) hn prevent repetilion of the occurreince and )I similar occurrences.


The sum of the total outage hours plus the hours the generator was on line (item 7 of Appendix C) should equal the gross hours in the report ing period (item 1 of Appendix C).  Reason. Categorize by letter designation in accordance with the table appearing on the report form. If category H must be used, supply brief comments.
10. Failure Data: Where equipment failure is cause of the occurrence or equipment failed as a result o1f tile occurrence, the following inforilmlion should be provided: a. Record of previous failures :rmd inallfunctions it the affected systems and components or ot similar equipment.


Method of Shutting Down the Reactor or Reducing Power. Categorize by number designation in accordance with the table appearing on the report form. If category 4 must be used, supply brief comments.
b. Equipment identification (e.g.. componcMtt.


Corrective Actions/Comments.
mnufacturer.


Use this column to am plify or explain the reasons for each shutdown or signifi cant power reduction, with the corrective action taken, if appropriate.
natile plate data).'The cautse of [tie occurrence is described in Item 7."Designation of Apparent Cause of Occurrence." and Ihc action taken to bring the situation under control is disetss'cd in Item 6, "Description of Occurrence." Tlihest items should not be repeated in this discussion.


The Comments column entries should provide identification of each shutdown or significant power reduction that occurs as a direct result of a re portable occurrence on which a report has been or will be submitted. (This information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or not a reportable occurrence was involved.)
1.16-8}}
When a direct correlation can be made between a given shutdown and a specific reportable occurrence report, the Comments column entry should state the reportable occurrence report number and date.  Summary. Write a brief summary description
(3 to 4 sentences)
of the highlights of operation of the unit for the reporting month. Include any comments required by item 12 of Appendix C.1.16-14 APPENDIX E LICENSEE EVENT REPORT CONTROL BLOCK I.L...LILJ
1 6 LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYIE I TrE (ED W I I I -I I I I I I- 1 1 L 1 -1 9 14.. 15 25 26 30 31 32 REPORTREPORT
CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE 0 1C&deg;N'4J__--J
LJ LI IL -i I I I I I I I I I I I I I I I 11 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION
7 8 9 80 SII 7 89 80 9I~ I 7 8 9 SYSTEMCAUSE'
CT COMPONENT
8o CODE CODE COMPONENT
CODE SVUER, MANUFACTURER
VIOLATION
RAL Li L--iil i Li 7 89 101 11 12 17 431 44 47 48 CAUSE DESCRIPTION
Em I I 7 89 WrIn I1w o.7 89 FACILITY METHO STATUS % POWER OTHER STATUS DISCO\ SLI W Ii L i I L 7 8 9 10 12 13 44 45 ." OF yCONTENT M12 RE EASED OF RELEASEAMOUNT
OF ACTIVITY SL .I , N o 7 8 9 10 11 44 PERSONNEL
EXPOSURES
NUMBER TYPE OESCRIPTION
7 8 9 11 12 13i PERSONNEL
INJURIES NUMBER DESCRIPTION
S48 9 11 12 7 8 9 11 12 IERY DISCOVERY
DESCRIPTION
I I 46 LOCATION OF RELEASE so -J 80 I I ou SPROBABLE
CONSEQUENCES
7 BQ go LOSS OR DAMAGF TO FACILITY TYPE D'ESCRIPTION
7 89 10 s0 P PUBLICITY
7189 80 ADDITIONAL
FACTORS 9 80 9 -0 9 80 NAME: PHONE:*U.S.GODiERNMENT
PRINTING OFFICE.1988-202-292:6034B
LUJ 1S 7 8' 19 7 V m ow I tso I ow 1.16-15 UNITED STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, D.C. 20555 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 FIRST CLASS MAIL POSTAGE it FEES PAID USNRC PERMIT No. G-67}}


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Revision as of 19:51, 12 October 2018

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 Se US. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE

OF REGULATORY

STANDARDS REGULATORY

GUIDE 1.16 REPORTING

OF OPERATING

INFORMATION

Revision 1 October 1973 GUIDE

A. INTRODUCTION

SCction 50.36. "TTechnical Specifications." of 10 CFR Part 50, "Licensing ot Production and Utilizationi Facilities," requires that easch applicant for a license authorizing operation of a nuclear power plant include in his applica tion proposed technical specifications.

These technical specifications as approved by the AE-C are incorrporated into tire facility license and are conditions oif the license. The technical specifications for nuclear power plants include a section on reporting requirements.

In addition to the reporting requirements necessary for compliance with the technical specifications of the license, there are specific reporting requirements included in Part 50 as well as in Parts 20.40. 70. and 73 of Title 10. For the convenience of licensees, these specific reporting requirements are included in the reporting program described in this guide. Each report discussed in this guide is either required by AEC regulations or is normally specified in licensees'

technical specifications.

In some cases this program may need to be supplemented or modified because of unique plant design features or other factors.The need for a supplemental or modified program will be determined on an individual-case basis. The Advisory Committee on Reactor S'feguards has heen consulted concerning this guide and has concurred in the regulatory position.

B. DISCUSSION

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 following the startup of the facility.In addition to those reports that relate to the safety of operation of the plant, the information on nuclear materials safeguards that must be reported pursuant to the ('omliission's regulations is also included.

The AEI'Regulatory staff has ieviewed Ihe types sf inorloratislat needed. Based oln !tis review and a review irf licensees'

current reporting pt igrai.; the staff has developed guidelines fotr such repirtint..

Thik ituidc presents an acceptable reporting prourainn I ol powel reactor licensees.

Ta hles I and II o1 this guide are coilpilaliotm.s of tinme limits or frequency

inlervals

[tr subhnlitting routline and nonroutline report:,.

Acceptable repoirtlin1 programs tor radioactive eflluents and environnmen.tal monitoring are presented in Regulatory Guides 1.21 (Safety Gtmide 211. "Measuring and Reporting oft'Effluents from Nuclear Pow\ver :lait<. and 4.1"'Measuring and Reportine ofi' R:idioct'livilt itl the Environs of Nuclear Power P1lhnts."'

respectively.

Significant differences in Revision I of this guide from Regulatory Guide 1.16o formerly Safety Guide 16)dated October 27, 1971 are: I. Extensive quoting of the Commission*, regulations has been deleted. References to the appropriate portiots of the Commission's regulations are included itt Tables I and !1 of this guide.2. For ease of reference the reporting summary table included in the original guide has been divided into two tables (Routine Reports and Nonroutine Reports)3. Reporting requirements have been updated ti reflect changes in the Comnmission's regulations and the reports required by the technical specifications.

4. Appendix A of this guide. "Standard iormtatl I't Reporting Abnorinal Occuirrences." ha,: h'etn added to give guidance to licensees suhmittinzg abnormal occurrence reports."Lines indicatc substantive chaivs O'wn10 plcvihitls issli

e. 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 avr table to the public Attention:

Director of Regulatory Standards.

Comments and wu9grtiodls tfo methods acceptable to thP AEC Regulatory stalf ot Implementing

&peailic paris 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 ih not 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 6. Products the issuance or continuance of a permit or license by the Commission.

2. RePearch and Test Reactors 7. T samotatne 3. Fuels ant] Materials Facilities

8. Occuttationiri Hal h Published guides will be revised periodically, as a~ptopriate, to accommodalte

4, Envitonmntol and Siting 9. Ar-rtruit Rr.v,ewv commentS and to reflect new information or eaperience.

5. Materials and Plant Protection

10. Genetal ,, ,III ]11 II

  • II I- ---

C. REGULATORY

POSITION The following reporting program should be used to implement the reportintg requirements of 10 CFR Parts 20, 40. 50. 70. 73, and teporting requirenments imposed by the AEC as license conditions.

including those reports required by thie tclnlical specilrCations.

1. Routine Reports a. Operations Reports'I I ) Startup Report. A summary. report of plant startot) and power escalation testing should he submittcd I'o0lowitrg reccipi t it' ai upctatintg license, tollowing an amendment it the licenise involving -a planned increase in power level. ft,..owin iv the iLnstall.'tinn of rrel il has if different design ur hlas been nranuutfactrrred by a different fuel supplier.

or fIOllowing modi fications dial nay haive signifilcantly ahlrred the nuclear. thermal. or hydranlic perftorniance iI" Ithe pl:ant. The report should include a description of The

';iltiues tit' the ocerating conditions or ctharacteristics obtained during the test progratn and a comnparison of these values with design predictions and specifications.

Any corrective actions that Were requ.ired to obtain sattisfactlotv operarior should also he' dcr itwcd. Sr rtrup reporls sluimld lie slrblnlilrled willitm I1) 10 clays following cormpletion of Ire stalt tip test ptoi gra in. (2) 90 days following resturnpli cr rit ior c ntten nt o1f c rommerciaI

po'wer operation.

or 31 t ) nronths following initial criticality.

whichever is earliest.

If thie Startutp Report does not cover all tihrec cverrts. i.. initiial criticalily.

cotmlpletion ot S :c rl tip t st C plro ra iii. rod resl rillpt loll or ce to nmterncete.

of :o Inetrrc ial poe'r operatiion.

Suplplementa'ry rep.crts Slhou.ld he srtbitritted at least every lthrce trit ;i ll! hi c evonts are t.orrpleted.

(2) First Year Operaton Report. A report sh1trld hC subnrittled wit hin 60 days aftier completion of the first year oit operalion.

This .tar begi ms oc coltplet ion tt'o all three evetlt s listed in C.;.a.i i ). This report mtay he incorpor:ated into tile semiatrtrtl olperatrino relport rard shurld cover tire following:

(:ill ;m ,n v:ltr;!tit1In

'; plhrtl ltcc hi dale in corinlprisim wi! Ii 'sicti !tiedicticlns and S1 O: ilic.l iI jihltilsl' ,ilil subriitied Witlh the license application i1" measured operating characteristics indicate that there may be substantiialvariance fronm prior analyses:2 (c) an assessrenrt of file performance of strtctures.

sysletrs.

and components iml'-rtant to safety: thill iti, Ca, L !,. l. .1titihctcld bhe S.tllrith:

ill writirg tI0 Ie I)reclror or r th I e ;Ipprlrltialte AViC Re utailort -(i,,cration n Regionial Office.2I'rciously r it rit tedl sal % ;! raysi.s repo r r i V.inLccrloritlcl hb t eretilrce.(d) a progress and status report oir airy items identified as requiring additional inforitation during tire operating license review or during the startup of tlie facility, including ilemns discussed in tile AEC's Safely Evaluation Repmrt and Supplements, items on which additional information was required as a conrdition of the license. and itemrs identified in the licensee's st:artup report: and (e) a report of measured in-plant radiation levels which are greater thiran those estimated irr the final safety analysis report by a factor of two or more.(3) Semiannual Operating Reports? Routine operating reports covering tire operation o tIrh pre2 us h (I mionths should be subtrmitted witiirt 60 days after Jartnuary I and Jtly I of each year. The initial report shtitld he stthlirited Withint 00 days after the cild iI' the first six-nmonth period during which initial criricalily took place. Fa ch report should inelnrde the followirrg: (a) Operations Sumrnmar'.

A stinrirary of operating experience occurring during the reportiog period that relates to tire s:icu operation of the facility.including a sumnmary of: (i) changes in facility design.(it) performance characteristics (e.g..eqttipreti t ;tnid fuel per formlance), (iii) changes in) operating procedutres which were necessitated by (i) and (ii) above or which otherwise were required to improve thie saklty of operations, (iv) results of surveillance tests and inspections required by the licensee's technical speciftications.(v) the results of aniy periodic cottainment leak rate tests performed during the reporting period.(vi) a brief suimmary of tirosk cihtanges.

tests. and experiments requiring auLthorization from the Commission purtntant to 10 CMR 50.59(a), and (vii) any chanrges in thie p1lnt operating staff for thiose positions designated as key stipervisory personniel positions in the technical specificairs.(b)powet generated Power Generation.

A sumnnmary of during the reporting period including: (iM gross thermal power geterated (itn MWI 1).(ii) gross electrical power generated (in MWH), (iii) number of iours tire reactor was critica!, (iv) number of hours the generator was on line, and (v) histogram of thermal power vs.t if e.'A sinrde subliimr itl may be imadrde for a multiple facility mat iim. The stticrrthittal shiould corritine tinrow. eclions Irh are comllrrrlrn iI all I'acilitics at ilre station.I .I0c-2 I *(c) Shutdowns.

Descriptive material covering all outages occurring during the reporting period. For each outage, information should be provided oil: (i) tile cause of the outage, (ii) the inethud of shutting down the]reactor;

e.g.. trip, automatic rundown, or manually controlled deliberate shutdown'(iii) duration of the outage (in hours), (iv) plant status during the outage'e.g.. cold shutdown or hot standby, and (v) corrective action taken to prevent repetition, if appropriate.(d) Maintenance.

A discussion of corrective maintenance (excluding preventive maintenance)

performed during the reporting period on safety-related systems and components4 and on systems and components that reduce or prevent the release of radioactive materials to the environs.

For any malfunction for which corrective maintenance was required, information should be provided on: (i) t he system or component involved, (ii) the cause of the malfunction.(iii) the results and effect on saf.operation.

and (iv) corrective action taken to prevent repetition.(e) Changes, Tests and Experiments.

A brief description and the summary of the safety evaluation for those changes, tests, and experiments, carried out without prior Commission approval pursuant to the provisions of IOCFR 50.59(b).(f) Primary Coolant Chemistry.

A tabulation on a monthly basis of the maximum. average, and minimum values for the following primary coolant system parameters: (i) Gross radioactivity in pCi/ml.(ii) Suspended solids in parts per million.(iii) Gross tritium in pCi/ml.(iv) Iodine 131 in pCi/ml, (v) Ratio of Iodine-131 to Iodine-I133.(vi) Hydrogen in cc per kg.(vii) Lithium in parts per million.(viii) Boron-lO in parts per million.(ix) Oxygen-16 in parts per billion, (x) Chloride in parts per million, and (xi) pH at 25 0 C.4Those plant features necessary to assure the integrity of the reactor coolant pressure boundary.

the capability to shut down the reactor and maintain it in a jal'vo shtdown condition.

or the capability to prevent or miti~oc tite consequences of1 accidents which could result in o.itc e,'i.sures comparable to the guideline exposures of 10 CFR Part 100.(g) Occupational Personnel Radiation Exposure i) A tabulation of 0i1e titinher Of occupational personnel exposures for plan' operations personnel (permanent and temporary)

in the following exposure increments for the reporting period: less thatn 100 mrerm, 100-250 ortem. 250-500 ntoem. 5001-750 morem, 750-1000 mrem. 1-2 rem. 2.3 retn. 3.4 rem. 4-S rem, 5.6 rem, and greater than 6 remi.(ii) A tabulation of the nurniter ot'personnel receiving more than 500 mrem exposure in the reporting period according to duty function le.g..routine plant surveillance and inspection (regular duty), routine plant maintenance, special plant mainten:itce (describe maintenance).

routine fueling operation.

special refueling

(,peration (describe and other job-related exposures.](iii) A tabulation annually of the number of personnel receiving more than 3 rein atnd fie major cause(s).(hi) FSAR Changes. Submission of revised FSAR pages on a replacement page basis appropriately r7epared for direct insertion into the applicable FSAIR section and describing all safety.related chaniges in'facility design. method of operation.

revised safety or transient analysis.

or f:,cility equipment additiots.

Also a listing of effective pages by date of revision or revisiotn number should be submitted.

b. Additional Routine Reporting Requirements.

Table 1 lists routine reports required by 10 CFR Parts 20. 40, 50. and 70. including those listed in Regulatory Position C.I .a.2. Nonroutine Reports a. Reporting of Abnormal Events (1) Abnormal Occurrence Reports. A 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 and telegraph to the Director of the appropriate AlFC Regulatory Operations Regional Office. (cc to the Director of Licensing)

followed by a written report wihrin 10 days to the Director of the appropriate AlEC Regulatory Operations Regional Office in the event of an abnormal occurrence.

Appendix A of this guide, "Standaid Format for Reporting Abnormal Occurrences.-

should be used as guidance when submitting abnotmtal occurrence reports.Abnormal occurrences are defined in the definitions section of the licensee's technical specifications and usually include, as a miniutitll, items (a) through (h) of this paragraph.

1 1 -3 (a) A safety. systeil setting- :ess conlservative titan the limiting setting, established in the technical specifications.(b) Conditions which result in a limiting condition for operations established in the technical specilfications not being met.'0 Abnormal degradation of one of thie several boundaries designed to contain radioactive materials.(d) An unplanned or uncontiolled release of radioactive material from the site boundary.(e) Uncontrolled or unanticipated changes in reactivity "qual to or greater than 1% Akikk.(') Incidents or conditions which prevented or could have prevented the performance of thle intended safely function of an engineered safely feature system or of the reactor protection system.(g) Observed inadequacies in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connection with tile opelation of the plant.(h) Conditions arising from natural of man-made events that affect or threaten to affect the sale operation of the plant.(2) Reporting of Unusual Events. A written report should be forwarded within 30 days to the Director of t(ie appropriate AEC Regulatory Operations Regional Office, in the event of: (a) Discovery of any substantial errors in the transient or accident analyses, or in the methods used for such aitalyses.

as described in the Safety Analysis Report or in the bases for the technical specificat ions.(b) Discovery of any substantial variance from performance specifications contained in the technical specifications or in thle Safety Analysis Report.(c) Discovery of any condition involving a ipossible single failure which. for a system intended to be designed against assumed single failures.

could result in a loss of the capability Of the system to perform its safety'loun ion.b. Additional Nonroutine Reporting Requirements Table II lists nonroutine reports required by 10 CFR Parts 20. 40, 50, 70, and 73. including those listed in Regulatory Position C.2.a.i 5A~ defined in 10CF]R 50.36(c).1.16-4

0e Requirement T'SI TS TS§20.407§20.408§40.64(a)§40.64(a)§40.64(b)§50.59(b)§70.53§70.54§70.54 Appendix G to 10 CFR Part 50 Appendix H to 10 CFR Part 50 Appendix J to 10 CFR Part 50 Startup First Year (Semiannual Personnel E Personnel E Employmen Transfer of Receipt of , Source Mate Changes, Te Special Nuc.Transfer of Receipt ofS Fracture To TA8LE I REPORTING

SUMMARY-ROUTINE

REPORTS*Report Timing of Submittal 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.)perat.on Within 60 days after completion of the first yeat of operation.

Within 60 days after January Iand July I of each year.xposure and Monitoring Within first quarter of each calendar year.xposure on Termination of Within 30 days after the exposure of the individual has it or Work been determined or 90 days after date of termination of employment or work assignment.

whichever is earlier.Source Material Promptly upon transfer.ource Material Within 10 days after material is received.erial Inventory Within 30 days after June 30 of each year.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 year.Special Nuclear Material Promptly upon transfer.Special Nuclear Material Within IK days after material is received.ughness On an individual-case basis at least 3 years prior to the 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.ssel Material Surveillance Completion of tests after each capsule withdrawal.

ntainment Building Approximately

3 months following conduct of test..eak Rate Test Reactor Ve Reactor Con Integrated L ITechnical Specifications

1.16-S

A 4 ..TABLE II REPORTING

SUMMARY-NON

ROUTINE REPORTS Initial Writtan Report Within 10 days 15 days 30 days 3 mo Requirement Report Notification T'I TS Abnormal Occurrence Unusual Events Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> X§20.405§20.402 Overexposures and Excessive Levels of Radiation and Concentration of Radioactive Material X X X Theft or Loss of Material Immediately

§20.403(a)

Severe Accident lnvolhiir Licensed Material§20.403(b)

Accident Involving Licensed Material Imnediately Within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s§40.64(c)§ 50.59(d)§ 70.52§ 73.42 Theft or Unlawful Diversion of Source Material Authorization of Cl, "cs,.and Experiments Accidential Criticality or Loss of Special Nuclear Material Unaccounted for Shipments.

Suspected Theft. or Unlawful Diversion of Special Nuclear Material Prompt ly X IP'rotmplvl I tmnmediately X 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 ur:l :c'.ls.I .16-6 A 9 t.-a 0 APPENDIX A STANDARD FORMAT FOR REPORTING

ABNORMAL OCCURRENCES

The standard format for submission of abnormal occurrence reports (AOR) identifies the principal information that should be contained in a completed AOR and gives a' format for presenting it. In the course of reviewing past AOR's the AEC Regulatory staff has found a wide variance in the type and detail of information reported.

To assure that AOR's submitted are consistent both in format and in the principal information included, the format for abnormal occurrence reports presented below should he usci and the information requested should be submitted when applicable.

If investigation is not complete by the time the initial report is submitted, the licensee should so indicate and give estimated time when a supplemental report will be submitted.

STANDARD FORMAT FOR ABNORMAL OCCURRENCE

REPORTS Report Number: .(1)Report Date: (2a)Occurrence Date: (2b)Facility:

(3)Identification of OccUrrence:

(4)Description of Occurrence:

(6)Designation of Apparent Cause of Occurrence:

(7)Design Manufacture Installation/Construction-Operator-Procedure-Unusual Service Condition Including Environmental-Component Failure-Other (specify)Analysis of Occurrence:

(8)Corrective Action: (9)Failure Data: (10)Conditions Prior to Occurrence:

(5)-Steady-State Power-Hot Standby-Cold Shutdown-Refueling Shutdown-Routine Startup Operation-Routine Shutdown Operation Load Changes During Routine Power Operation-Other (Specify)NOTES TO AOR STANDARD FORMAT I. Report Number: Abnormal occurrence reports should be numbered sequentially on a calendar-year basis for each facility (or each unit of a multi-unit site) using the facility (unit) docket number as the principal identifier (e.g., Docket NumberJYear-Sequential Number in calendar year).Supplementary reports should be numbered using alphabetical identifying letters following the principal report number (e.g., Docket Number/Year-Sequential Number in calendar year-alphabetical letter identifying supplementary report.)2. Report Date: Date occurrence.

of (a) report submitted and (b)3. Facility:

Name and location of facility.4. Identification of Occurrence:

The abnotmal occurrence should be identified by a short title'which identifies the type of abnormal occurrence and the system, component.

or even, involved.(Regulatory Position C.2.a.(I)

should be used as a guide for listing the type of abnorml occurrence.)

1.16-7 a S. Conditions Prior to Occurrence:

Thie applicable c:apf ion should be used followed by a description of plant status prior to tie abnormal occurrence.

Major plant parameters should be included.6. Description of Occurrence:

A chronological sequence of events should be described in an objective manner. The following should be included: a. Method of detection and time of detection.

b. Step-by.step sequoence of events identif'ying all protection system :tctions and operator actions to hrmig fhc sitation under control.7. Designation of Apparent Cause of Occurrence:

The single apparent cause should be identified and narrated.

When other causes contributed to the abnormal occurrence.

the narrative of the apparent cause should discuss fully the single cause assigned and the contributing causes assigned.8. Analysis of Occurrence:

The abnormal occurrence should be analyzed for safety implications.

The analysis of effect." and the attendant consequences should include tile following information, as applicable:

a. Maximum and ,minimum conditions during transients.

b. Equipment malfunction.

c. Operator error.d. Damage to systems. components.

and structures.

e. Personnel injuries.f. Personnel exposures.

g. Quinmtity and composition of radioactive materials released.Ih. The consequences cr potential colsequnclies

ýfrom the standpoint of public healfli and safety.9. Corrective Action:' The following informalion should he provided: a. Correclive action lakcn (or to he laken) to correct tile abnormal occurrence.

It. Corrective action taketn (or to he i;keinL) hn prevent repetilion of the occurreince and )I similar occurrences.

10. Failure Data: Where equipment failure is cause of the occurrence or equipment failed as a result o1f tile occurrence, the following inforilmlion should be provided: a. Record of previous failures :rmd inallfunctions it the affected systems and components or ot similar equipment.

b. Equipment identification (e.g.. componcMtt.

mnufacturer.

natile plate data).'The cautse of [tie occurrence is described in Item 7."Designation of Apparent Cause of Occurrence." and Ihc action taken to bring the situation under control is disetss'cd in Item 6, "Description of Occurrence." Tlihest items should not be repeated in this discussion.

1.16-8


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