Regulatory Guide 1.16

Reporting of Operating Information - Appendix a Technical Specifications.

ML12305A256
Person / Time
Issue date:	01/31/1975
From:	Office of Nuclear Regulatory Research
To:
References
RG-1.016, Rev 3
Download: ML12305A256 (13)

Revision 3 January 1975 U.S. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE OF REGULATORY STANDARDS

GUIDE

REGULATORY GUIDE 1.16 REPORTING OF OPERATING INFORMATION-APPENDIX A

TECHNICAL SPECIFICATIONS

A. INTRODUCTION

addressees and designation of the number of copies re- quired, is included in Regulatory Guide 10.1, "Compila- Section 50.36, "Technical Specifications," of 10 tion of Reporting Requirements for Persons Subject t_0

CFR Part 50, "Licensing of Production and Utilization AEC Regulations," and is not presented-he-rein._

Facilities," requires that each applicant for a license authorizing operation of a nuclear power plant include in its application proposed technical specification

B. DISCUSSION

These technical specifications, as issued by the AEC, are incorporated into the facility license and are conditions In September 1974 the Regulatory staff published of the license. Technical specifications are now included Revision 2 of Regulatory Guide 1.16. This revision re- as two appendices to the license: Appendix A technical flected results of a Regulatory staff review of operating specifications relate to health and safety, and Appendix intormation needed to permit assessment by the Com- B technical specifications relate to environmental im- mission of safety-related activities during the operating pact.' Each of these appendices includes a section on phase of plant life. Significant differences in this guide reporting requirements. The reporting program' described from Revision 1 of Regulatory Guide 1.16, dated Octo- in this regulatorv guide involves the reporting require- ber 1973, were:

ments of Appendix A technical specifications only. In 1. Reporting requirements were updated to reflect

"Osome cases, this program may need to be supplemented changes in reports required by Appendix A technical or modified because of unique plant design features or specifications. In general, these changes involved:

other factors. The need for a supplemental or modified a. a change in frequency of submittal of routine program will be determined on a case-by-case basis. operating reports;

0 Reporting of information concerning radioactive b. elimination of the first-year operating report;

discharges, radiological environmental monitoring, and c. formalization of reporting of operating infor- Q,-) nonradiological environmental surveillance and environ- mation on a monthly frequency;

• ( mental impact is discussed in Regulatory Guide 4.8,

"Environmental Technical Specifications for Nuclear Power Plants."

d. deletion of certain items of information no longer required by the AEC to be submitted on a routine basis;

In addition to the reporting requirements necessary e. changes in the format and immediacy of re- for compliance with technical specifications, specific porting required for certain types of abnormal occur- reporting requirements are included in Part 50, as well as rences; and in other Parts of Title 10, Chapter 1, Code of Federal f. improved guidance concerning definitions and Regulations. A compilation of all reporting requirements categories of significance of abnormal occurrences.

applicable to the various types of AEC licensees, in- 2. Appendices B, C, D, and E were added to provide cluding identification of the proper AEC addressee or the desired format for radiation exposure reports and monthly operating reports.

3. A listing of reports other than those required by

'A few facilities have a single appendix that contains the Appendix A technical specifications was eliminated. (See combined aspect of Appendices A and B. Introduction above.)

USAEC REGULATORY GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public Attention: Director of Regulatory Standards. Comments and suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of improvements in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques .red by the staff in of the Commission, U.S. Atomic Energy Commission, Washington, D.C. 20545, evaluating specific problems or postulated accidents, or to provide guidance to Attention: Docketing and Service Section.

applicants. Regulatory Guides are not substitutes for regulations and compliance with them is not required. Methods and solutions different from those set out in The guides are issued in the following ten broad divisions:

the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission. 1. Power Reactors

6. Products

2. Research and Test Reactors

7. Transportation

3. Fuels and Materials Facilities 8. Occupational Health Published guides will be revised periodically, as appropriate, to accommodate 4. Environmental and Siting 9. Antitrust Review comments and to reflect new information or experience. 5. Materials and Plant Protection 1

0. General

6 Comments were invited within 60 days of publica- scribed. Additional specific details may be included in tion of Revision 2 for use in conjunction with early license conditions based on the applicant's commitment revision of the guide. As a result of~comments received to applicable Regulatory guides and should be included -

on the guide and additional staff review, the Regulatory in this report.

staff has developed Revision 3 to Regulatory Guide Startup reports should be submitted within (1)

1.16. 90 days following completion of the startup test Significant differences in this guide from Revision 2 program, (2) 90 days following resumption or com- of Regulatory Guide 1.16, dated September 1974, are: mencement of commercial power operation, or (3) 9

1. The startup report was revised to be more specific as months following initial criticality, whichever is earliest.

to the test results to be reported. If the Startup Report does not cover all three events

2. The annual report section was revised to (1) further (i.e., initial criticality, completion of startup test pro- quantify the term "reduction in power," (2) provide gram, and resumption or commencement of commercial further guidance on reporting of occupational radiation power operation), supplementary reports should be sub- exposures, and (3) revise the information to be sub- mitted at least every three months until all three events mitted on fuel performance. have been completed.

3. The abnormal occurrence report section was revised to (1) provide for prompt notification by telephone and confirmation of such notification by telegraph, mail- b. Annual Operating Report.', 23 gram, or facsimile transmission of the types of abnormal occurrences listed under Section 2.a, (2) be more Routine operating reports covering the opera- specific on the types of abnormal occurrences reported, tion of the unit during the previous calendar year should

(3) delete radiological effluent releases from Appendix A be submitted prior to March 1 of each year. The initial technical specification reporting requirements, (4) pro- report should be submitted prior to March 1 of the year vide for reporting of the types of abnormal occurrences following initial criticality.

listed under Section 2.b within 30 days of occurrence of The primary purpose of annual operating the event, and (5) make Section 2.c of Revision 2 of the reports is to permit annual evaluation by the AEC staff guide a separate section (Section 4). of operating and maintenance experience throughout the nuclear power industry. The annual operating reports made by licensees should provide a comprehensive sum-

C. REGULATORY POSITION

mary of the operating experience gained during the year,l even though some repetition of previously reporte In addition to the applicable reporting requirements information may be involved. References in the annual of Title 10, Code of Federal Regulations, the following operating report to previously submitted reports should program for reporting of operating information provides be clear.

an acceptable basis to the Regulatory staff for meeting Each annual operating report should include:

the reporting requirements of Appendix A technical (1) A narrative summary of operating expe- specifications. Reports submitted in accordance with rience during the report period relating to safe operation this guide should be addressed to the Director of the of the facility, including safety-related maintenance not appropriate Regulatory Operations Regional Office covered in item 1.b.(2)(e) below.

unless otherwise noted. (2) For each outage or forced reduction in power 4 of over 20 percent of design power level where

1. Routine Reports the reduction extends for greater than four hours:

(a) the proximate cause and the system a. Startup Report. and major component involved (if the outage or forced reduction in power involved equipment malfunction);

A summary report of plant startup and power escalation testing should be submitted following (1)

receipt of an operating license, (2) amendment to the

2 license involving a planned increase in power level, (3) A single submittal may be made for a multiple unit installation of fuel that has a different design or has been station. The submittal should combine those sections that are manufactured by a different fuel supplier, and (4) common to all units at the station.

modifications that may have significantly altered the S'Much of the information in the Annual Report was nuclear, thermal, or hydraulic performance of the plant. previously submitted in a Semiannual Report.

4 The term "forced reduction in power" as ued in this guide The report should address each of the tests identified in and as normally defined in the electric power industry means the the FSAR and should in general include a description of occurrence of a component failure or other condition which the measured values of the operating conditions or requires that the load on the unit be reduced for corrective characteristics obtained during the test program and a action immediately or up to and including the very next week- comparison of these values with design predictions and end. .Note that routine preventive maintenance, surveillance, and specifications. Any corrective actions that were required calibration activities requiring power reductions are not covered to obtain satisfactory operation should also be de- by this section.

1..16-2

(b) a brief discussion of (or reference to Office, to arrive no later than the tenth of each month

• reports of) any abnormal occurrences pertaining to the following the calendar month covered by the report.

Ioutage or power reduction;

(c) corrective action taken to reduce the 2. Abnormal Occurrences probability of recurrence, if appropriate;

(d) operating time lost as a result of the Licensees are required to investigate and evaluate outage or power reduction (for scheduled or forced the significance of abnormal occurrences and implement outages,s use the generator off-line hours; for forced corrective actions to prevent recurrence, in accordance reductions in power, use the approximate duration of with provisions of technical specifications and the pro- operation at reduced power); gram for quality assurance during the operational phase (e) a description of major safety-related of plant life. In addition, abnormal occurrences, in- corrective maintenance performed during the outage or cluding corrective actions and measures to prevent reoc- power reduction, including the system and component currence, should be reported to the AEC as described involved and identification of the critical path activity below.

dictating the length of the outage or power reduction; In general, the importance of an occurrence and with respect to safety significance determines the (f) a report of any single release of radio- immediacy of reporting required. In some cases, how- activity or radiation exposure specifically associated ever, the significance of an event may not be obvious at with the outrage which accounts for more than 10 per- the time of its occurrence. In such cases, the AEC should cent of the allowable annual values. be informed promptly of an increased significance in the

(3) A tabulation on an annual basis of the licensee's assessment of the event. In addition, supple- number of station, utility, and other personnel (in- mental reports may be required to fully describe final cluding contractors) receiving exposu'res greater than resolution of occurrence. In some cases of corrected or

100 mrem/yr and their associated man-rem exposure supplemental reports, a licensee event report should be according to work and job functions, 6 e.g., reactor completed and reference should be made to the original operations and surveillance, inservice inspection, routine report date. Guidance concerning reportable occurrences maintenance, special maintenance (describe mainte- that should be reported in different time frames is pro- nance), waste processing, and refueling. The dose assign- vided below.

ments to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge.measurements. a. Prompt Notification With Written Followup.

• ,iSmall exposures totalling less than 20 percent of the individual total dose need not be accounted for. In the The types of events listed below should be aggregate, at least 80 percent of the total whole body reported as expeditiously as possible, but within 24 dose received from external sources should be assigned hours by telephone and confirmed by telegraph, mail- to specific major work functions. See Appendix B to this gram, or facsimile transmission to the Director of the guide for a standard format for providing this infor- appropriate Regulatory Operations Regional Office, or mation. his designate, no later than the first working day fol-

(4) Indications of failed fuel resulting from lowing the event, with a written followup report within irradiated fuel examinations, including eddy current two weeks. The written followup report should include, tests, ultrasonic tests, or visual examinations completed as a minimum, a completed copy of the licensee event during the report period. report form (see Appendix A to this guide) used for entering data into the AEC's computer-based file of in- c. Monthly Operating Report. formation concerning licensee events. (Instructions for completing these license event report forms7 are issued Routine reports of operating statistics and shut- individually to each licensee.) Information provided on down experience should be submitted on a monthly the licensee event report form should be supplemented, basis. The report formats set forth in Appendices C, D, as needed, by additional narrative material to provide and E to this guide should be completed in accordance complete explanation of the circumstances surrounding with the instructions provided. The completed forms the event.

should be sent to the Director of Regulatory Operations, (1) Failure of the reactor protection system or U.S. Atomic Energy Commission, Washington, D.C. other systems subject to limiting safety-system settings

20545, with a copy to the appropriate RO Regional to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety-system setting in the technical specifi- sThe term "'forced outage" as used in this guide and as cations or failure to complete the required Protective normally defined in the electric power industry means the occur- rence of a component failure or other condition which requires

• 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 § 20.407 'Instruction Manual, Licensee Event Report File, Office of of 10 CFR Part 20. Operations Evaluation, USAEC, Washington. D.C. 20545.

1.16-3

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

(c) Failure of the reactor protective sys- (5) Failure or malfunction of one or more tem to complete the required protective action once components which prevents or could prevent, by itself, initiated. the fulfillment of the functional requirements of sys- tem(s) used to cope with accidents analyzed in the SAR.

Note: Instrument drift discovered as a result of testing The following are examples:

need not be reported under this item but may be report- (a) Clogged fuel line(s) resulting in failure able under items 2.a(5), 2.a(6), or 2.b(l) below. to supply fuel to the emergency generators.

(b) Multiple instrument drift resulting in

(2) Operation of the unit or affected systems loss of protective function.

when any, parameter or operation subject to a limiting (c) HPCI failure to start or failure to con- condition for operation is less conservative than the least tinue running once initiated.

conservative aspect of the limiting condition for opera- (6) Personnel error or procedural inadequacy tion established in the technical specifications. The which prevents or could prevent, by itself, the fulfill- following are examples: ment of the functional requirements of systems required (a) Shutdown not begun within the speci- to cope with accidents analyzed in the SAR. The fol- fied time when unidentified reactor coolant leakage lowing are examples:

exceeds the technical specifications limit. (a) Failure to restore a safety system to (b) Failure of a system other than the operability following test or maintenance.

systems subject to limiting safety-system settings (see (b) Improper procedures leading to incor-

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

(c) Operation with unacceptable contain- ment leak rate type B or C test results. Note: For items 2.a(5) and 2.a(6) reduced redundancy (d) System cooldown at a rate exceeding that does not result in loss of system function need not the technical specifications limit. be reported under this section but may be reportable under items 2.b(2) and 2.b(3) below.

Note: If specified action is taken when a system is found to be operating between the most conservative (7) Conditions arising from natural or man- and the least conservative aspects of a limiting condition made events that, as a direct result of the event, require for operation listed in the technical specifications, the plant shutdown, operation of safety systems, or other limiting condition for operation is not considered to protective measures required by technical specifications.

have been violated and need not be reported under this The following are examples:

item, but it may be reportable under item 2.b(2) below. (a) Threatened civil disturbances requiring plant shutdown.

(3) Abnormal degradation discovered in fuel (b) Damage to the facility caused by fire, cladding, reactor coolant pressure boundary, or primary flood, earthquake, or other similar occurrences.

containment. The following are examples: (8) Errors discovered in the transient or acci- (a) Through-wall failure of piping or com- dent analyses or in the methods used for such analyses as ponents of the reactor coolant pressure boundary. described in the safety analysis report or in the bases for (b) Steam generator tube thinning in the technical specifications that have or could have per- excess of acceptance limits in Regulatory Guide 1.83, mitted reactor operation in a manner less conservative

"Inservice Inspection of Pressurized Water Reactor than assumed in the analyses. The following are exam- Steam Generator Tubes." pies:

(c) Welding or material defects greater (a) Loss of condenser vacuum resulting in than those allowable by applicable codes. reactor pressure and flux transients that peak at values higher than analyzed.

Note: Leakage of valve packing or gaskets within the (b) Reactivity insertion delay times by re- limits for identified leakage set forth in technical specifi- actor protection system longer than those used in the cations need not be reported under this item. technical specification bases.

(9) Performance of structures, systems, or

(4) Reactivity anomalies involving disagree- components that requires remedial action or corrective ment with the predicted value of reactivity balance measures to prevent operation in a manner less conserva- under steady state conditions greater than or equal to tive than that assumed in the accident analyses in the

1.16-4

safety analysis report or technical specifications bases; or graded mode permitted by a limiting condition for discovery during plant life of conditions not specifically operation, or plant shutdown required by a limiting considered in the safety analysis report, or technical condition for operation. The following are examples:

• specifications that require remedial action or corrective (a) Core spray pump breaker tripped after measures to prevent the existence or development of an 20 minutes during test. Trip unit was found to be defec- unsafe condition. The following are examples: tive, declared inoperable, and repaired.

(a) Axial flux ratios less conservative than (b) Safety injection pump failed to start those for which correlations with overpower AT were following system initiation. Required surveillance on based on core burnup projections. redundant components was successfully completed.

(b) Failure of a safety injection pumpto (c) One of the two centrifugal charging deliver the flow rates assumed in the FSAR. pumps became inoperable because of a faulty bearing.

(c) Degradation of hydraulic shock sup- Redundant pump operability, was confirmed.

pressors to the extent that they could not perform their required safety function. Note: Routine surveillance testing, instrument calibra- (d) Failure of magnetic trip mechanisms tion, or preventive maintenace which require system on a safety-related circuit breaker to provide trip on configurations as described in items 2.b(l) and 2.b(2)

instantaneous overcurrent as indicated on the manufac- need not be reported except where test results theni- turer's time-current characteristic curve. selves reveal a degraded mode as described above.

(e) Failure of a safety/relief valve to close after pressure has reduced below the required reseat (3) Observed inadequacies in the implementa- valve., tion of administrative or procedural controls which (f) Thermal shock to the reactor coolant threaten to cause reduction of degree of redundancy system resulting from inadvertent safety injection actua- provided in reactor* protection systems or engineered tion. safety feature systems. The following are examples:

(a) One of the three diesel generators Note: This item is intended to provide for reporting of tripped from high temperature because cooling water potentially generic problems. valves were lined up incorrectly.

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

Trip of switch would not occur at low pressure. Im- The abnormal occurrences discussed below have proper return to operation following maintenance was

• lesser immediate importance than those described under the cause.

'2.a above. Such events should be the subject of written (c) Failure to perform surveillance tests at reports to the Director of the appropriate Regulatory the required frequency.

Operations Regional Office within 30 days of occurrence (4) Abnormal degradation of systems other of the event. The written report should include, as a than those specified in item 2.a(3) above designed to minimum, a completed copy of the licensee event report contain radioactive material resulting from the fission form (see Appendix A to this guide) used for entering process. For example, a through-wall leak in a liquid data into the AEC's computer-based file of information waste storage tank.

concerning licensee events. (Instructions for completing these licensee event report forms 7 are issued individually Note: Sealed sources or calibration sources are not in- to each licensee.) lnformation'provided on the licensee cluded under this item. Leakage of valve packing or event report form should be supplemented, as needed, gaskets within the limits for identified leakage set forth by additional narrative material to provide complete in technical specifications need not be reported under explanation of the circumstances surrounding the event. this item.

(1) Reactor protection system or engineered safety feature instrument settings which are found to be 3. Unique Reporting Requirements less conservative than those established by the technical specifications but which do not prevent the fulfillment The above reporting program will in general satisfy of the functional requirements of affected systems. The the reporting requirements necessary for compliance following are examples: with Appendix A technical specifications. This program (a) One of the four scram dump volume may need to be supplemented or modified because of level switches failed to operate during surveillance test.. unique plant design features or other factors. The need (b) One of four reactor low-pressure for a supplemental or modified program will be deter- switches operated at 885 psig instead of LSSS value of mined on a case-by-case basis and so designated in in-

900 psig. dividual operating licenses.

(c) During test, one out of four under- voltage relays failed to perform its function of tripping a 4. Events of Potential Public Interest reactor trip breaker.

(2) Conditions leading to operation in a de- The types of events listed below are frequently of

1.16-5

high public interest. While some of the events may not if the time for repair is likely to exceed the time allowed be reportable by regulation or defined in other parts of by the technical specifications.

this guide, the Director of the appropriate Regional Office, or his designate, should be informed of such

D. IMPLEMENTATION

events by telephone as soon as possible after the event has been discovered. The purpose of this section'is to provide informa- tion to applicants and licensees regarding the Regulatory a. An event that causes damage to property or staff's plans for utilizing this regulatory guide.

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

quire action which need not be reported under item - For licensees holding operating licenses without

2.a(7) above. Appendix B environmental technical specifications, it d. Discovery of significant radiological event off- may be necessary to in-l'd-eftse irepofrilntifie in

.RdgUoa_ Guide 1.21, "Measuring, Evaluating, and site occurring during transport of material for which the licensee was either shipper or consignee. Reporting Radioactivityin Solid Wastes and Releases of e. Unscheduled shutdowns expected to last for Radioactive Materials in Liquid and Gaseous Effluents more than one week, regardless of cause. from Light-Water-Cooled Nuclear Power Plants," and f. Unusual releases of radioactive material from Regulatory Guide 4.1 "Measuring and Reporting of the site boundary not reportable under other require- Radioactivity in the Environs of Nuclear Power Plants,"

ments. in the technical specifications under the unique re- g. Failure of or damage to safety-related equip- porting requirements section of the technical specifi- ment which need not be reported under item 2.a above, cations.

1.16-6

APPENDIX A

LICENSEE EVENT REPORT

CONTROL BLOCK I I I I I I

1 6 LICENSEE LICENSE EVENT

NAME LICENSE NUMBER TYPE TYPE

FFI

II II I I 1 I-I I ,1 I iI-I

9 14 15 2 E

26 R

REPORT REPORT EVENT DATE

DOCKET NUMBER REPORT DATE

CATEGORY TYPE SOURCE

NT 7 59 .60 61 68 69 74

~I II 1 EVENT DESCRIPTION

7 89 80

0o3111

7 89

0O41

7 89 80

0o51

7 89 so

7 8 9 PRIME 80

SYSTEM CAUSE COMPONENT COMPONENT

CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER VIOLATION

W L I I I WI Li I I1 I Li

7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION

I I

7 89 80

s 7 89 I

80

I IETHOD OF

w 1 FACILITY

STATUS

Li I

%POWER

I I I jI

OTHER STATUS

_

D ISCOVERY

i5 1 DISCOVERY DESCRIPTION

I

7 8 9 10 12 13 44 4 16 a FORM OF 45 ACTIVITY CONTENT

RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

[ L L i 45 I

80

7 8 9 10 11 44 PERSONNEL EXPOSURES

M NUMBER TYPE DESCRIPTION

7 8 9 11 12 13

80  !

PERSONNEL INJURIES

NUMBER DESCRIPTION I

I

7 8 9 11 12 80

OFFSITE CONSEQUENCES

7A 1 LOSS OR DAMAGE TO FACILITY

78 TYPE

!o DESCRIPTION

PUBLICITY

78

7 89

0

ADDITIONAL FACTORS

7 89 so

19 I

7 8 9 8O

NAME* PHONE:

1.16-A-i

APPENDIX B

STANDARD FORMAT FOR REPORTING NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCTION

Number of Personnel (> 100 mrem) Total Man-Rem Contract Workers Contract Workers Work & Job Function Station Employees I Utility Employees and Others Station Employees I Utility Employees and Others Reactor Operations & Surveillance Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Routine Maintenance Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Inservice Inspection Maintenance Personnel Operating Personnel Health Physics Personnel

- Supervisory Personnel

- Engineering Personnel S Special Maintenance

- Maintenance Personnel Operating Personnel Health Physic s Personnel Supervisory Personnel Engineering Personnel Waste Processing Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Refueling Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel TOTAL

Maintenance Personnel Operating Personnel Health Physics Personnel Supervisory Personnel Engineering Personnel Grand Total i __ _ _ _ _ _ _ __ _ _ __ _ _ _ _ _ _ _ _ _ _ J_

I _ _ _ _ _ _ I _ _ _ _ _ _.1_I__ _ _ _ _ _ _

APPENDIX C

DOCKET NO.

UNIT

DATE

COMPLETED BY

AVERAGE DAILY UNIT POWER LEVEL

MONTH

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL

DAY (MWe-net) DAY (MWe-net)

1 17

2 18

3 19

4 20

5 21

22

7 23

8 24

9 25

10 26

11 27

12 28

13 29

14 30

15 31

16 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS

On this form, list the average daily unit power level in MWe-net for each day in the reporting month.

. Compute to the nearest whole megawatt.

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

1.16-C-1

APPENDIX D

UNIT

DATE

COMPLETED BY

DOCKET NO.-

OPERATING STATUS

I. REPORTING PERIOD: TTHROUGH

HOURS IN REPORTING PERIOD:

2. CURRENTLY AUTHORIZED POWER LEVEL.(MWth)____ - MAX. DEPENDABLE CAPACITY (MWe-NET)

3. LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED (IF ANY) (MWe-NET):

4. REASONS FOR RESTRICTION (IF ANY):

THIS CUMULATIVE

REPORTING PERIOD YR TO DATE TO DATE

5. HOURS REACTOR WAS CRITICAL .............

6. REACTOR RESERVE SHUTDOWN HOURS .......

7. HOURS GENERATOR ON LINE ...............

8. UNIT RESERVE SHUTDOWN HOURS ...........

9. GROSS THERMAL ENERGY

GENERATED (MWH) . .....................

10. GROSS ELECTRICAL ENERGY

GENERATED (MWH) ......................

11. NET ELECTRICAL ENERGY GENERATED

(M W H ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

12. REACTOR AVAILABILITY FACTOR (1) .........

13. UNIT AVAILABILITY FACTOR (2) ............

14. UNIT CAPACITY I-ACTOR (3) ...............

15. UNIT FORCED OUTAGE RATE (4) ............

16. SHUTDOWNS SCHEDULED TO BEGIN IN NEXT 6 MONTHS (STATE TYPE, DATE, AND DURATION OF EACH):

17. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

18. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) REPORT THE FOLLOWING:

DATE LAST DATE

FORECAST ACHIEVED

INITIAL CRITICALITY

INITIAL ELECTRICAL

POWER GENERATION

COMMERCIAL OPERATION

HOURS=REACTOR WAS CRITICAL X 100

(1) REACTOR AVAILABILITY FACTOR

HOURS IN REPORTING PERIOD

HOURS =GENERATOR ON LINE X 100

(2) UNIT AVAILABILITY FACTOR

HOURS IN REPORTING PERIOD

NFT ELECTRICAL POWER GENERATED

(3) UNIT CAPACITY FACTOR

MAX. DEPENDABLE CAPACITY (MWe-NET) X HOURS IN REPORTING PERIOD

FORCED OUTAGE HOURS

(4) UNIT FORCED OUTAGE RATE

HOURS GENERATOR ON LINE + FORCED OUTAGE HOURS

1.16-D-1

. I . ý

INSTRUCTIONS FOR COMPLETING OPERATING DATA REPORT

(APPENDIX D)

This report is to be furnished each month by licensees. 8. Unit Reserve Shutdown Hours. The duration in The name, telephone number and extension of the hours that the unit was removed from service for preparer should be provided in the space labeled economic or similar reasons, but was available for

"Completed By." The instructions below are provided to operation.

assist licensees in reporting the data consistently. The

9-10. Self Explanatory numbering of the instruction matches that used on the report format. 11. Negative numbers should be used, if applicable.

12-15. For units still in the startup and power ascension test phase, items 12-15 should not be computed.

OPERATING STATUS Instead, enter N/A in the current month column. These four factors should be computed starting at the time the

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

(0001, 750814 for 12:01 a.m. on August 14, 1975). 12. Reactor Availability Factor. Compute by Hours in reporting period should be calculated from dividing Hours Reactor was Critical (Item 5) by Hours in report period. Report Period (from Item 1). Express as percent, to

2. For the "net" figure, use Maximum Dependable nearest tenth of a percent. During months when the unit Capacity. Maximum Dependable Capacity is defined as is shut down for the entire period due to non-reactor the dependable main-unit capacity, winter or summer, problems, enter "Not Applicable." Do not include whichever is smaller. reserve shutdown hours in the calculation.

3. Note that this item is applicable only if 13. Unit Availability Factor. Compute by dividing restrictions on the power level are in effect.-Short-term Hours Generator On Line (Item 7) by Hours in Report (less than one month) limitations on power level need Period (from Item 1). Express as percent, to nearest not be presented in this item, since one of the important tenth of a percent. Do not include reserve shutdown purposes of the item is to determine if, and at what hours in the calculation.

power level, a restricted power level line should be 14. Unit Capacity Factor. Compute by dividing Net drawn on the chart of average daily reactor power. Electrical Energy Generated (Item II) by the product of Since this information is used to develop figures Maximum Dependable Capacity (MWe-net) (Item 2)

on capacity lost due to restrictions and because most times Hours in Report Period (from Item I). Express as users of the "Operating Plant Status Report" are percent, to the nearest tenth of a percent.

primarily interested in energy actually fed to the

15. Unit Forced Outage Rate. Compute by dividing distribution system, we request that this figure be Total Forced Outage Hours (from shutdown table, expressed in MWe (net) in spite of the fact that that figure must be derived from MWth or percent power. Appendix E) by the sum of flours Generator On Line (item 7) plus Total Forced Outage Hours (Appendix E).

4. Reasons for Restriction (if any). If item 3 is Express as percent, to nearest tenth of a percent.

used, explain in item 4. Brief narrative is acceptable. Cite references as appropriate. Indicate whether restrictions 16. Shutdowns Scheduled to Begin in Next 6 Months. Include type (refueling, maintenance, other),

are self-imposed or are regulatory requirements. Be as proposed date of start of shutdown and proposed length specific as possible within space limitations. Plants in of shutdown. It is recognized that shutdowns may be startup and power ascension test phase should be scheduled between reports and that this item may not be identified here.

all inclusive. Be as accurate as possible as of the date the

5. Self Explanatory report is prepared.

6. Reactor Reserve Shutdown Hours. The duration 17. Self Explanatory.

in hours that the reactor was removed from service for

18. Self -Explanatory. Note, however, that this administrative or other reasons but was available for information is requested for all units in startup and operation. power ascension test status, and is not required for units

7. Self Explanatory already in commercial operation.

'1.16-D-2

0 APPENDIX E DOCKET NO.

UNIT SHUTDOWNS UNIT NAME

DATE

COMPLETED BY

REPORT MONTH

TYPE METHOD OF

- F-FORCED DURATION SHUTTING DOWN

NO. DATE. S-SCHEDULED (HOURS) REASON (1) THE REACTOR (2) CORRECTIVE ACTIONS/COMMENTS

ON

(1) REASON (2) METHOD

A EQUIPMENT FAILURE (EXPLAIN) I --MANUAL

B MAINT. OR TEST 2 -MANUAL

C REFUELING SCRAM

D-REGULATORY RESTRICTION 3 --AUTOMATIC

E- OPERATOR TRAINING AND* SCRAM

LICENSE EXAMINATION

F- ADMINISTRATIVE

G- OPERATIONAL ERROR

(EXPLAIN)

H -OTHER (EXPLAIN)

SUMMARY:

INSTRUCTIONS FOR COMPLETING MONTHLY UNIT SHUTDOWN REPORTS

(APPENDIX E)

UNIT SHUTDOWNS It is recognized that some judgment is required in categorizing shutdowns in this way. In general, a forced This section should describe all plant shutdowns shutdown is one that would not have been completed in during the report period. In addition, it should be the the absence of the condition for which corrective action source of e-planation of significant dips in average was taken.

power levels (Appendix C). Each significant reduction in power level (greater than 20% reduction in average daily DURATION (HOURS)

power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) should be noted, even though the unit may not have been shut down Self explanatory. When a shutdown extends beyond completely.' For such reductions in power level, the the end of a report period, count only the time to the shutdown duration should be zero, the method of end of the report period and pick up the ensuing shutting down the reactor should be N/A, and the down time in the following report periods. Report Comments column should explain. The Comments duration of outages or significant reductions in power column should be used to provide any needed rounded to the nearest tenth of an hour to facilitate explanation not adequately described by the coded summation.

columns. Please do not add to the list of codes or legends now furnished. Similarly, do not add additional columns.

REASON

Categorize by letter designation in accordance with NUMBER the table appearing on the report form. If none of the specified categories can be used, supply brief comments.

This column should indicate the sequential number assigned to each shutdown or significant reduction in power for that calendar year. When a shutdown or METHOD OF SHUTTING DOWN THE REACTOR

significant power reduction begins in one report period and ends in another, an entry should be made for both Categorize by number designation in accordance report periods to be sure all shutdowns or significant with the table appearing on the report form. If none of power reductions are reported. the specified categories can be used, supply brief comments.

DATE

CORRECTIVE ACTIONS/COMMENTS

This column should indicate the date of the start of each shutdown or significant power reduction. Report as Use this column to amplify or explain as necessary.

year, month, and day. August 14., 1975 would be Where appropriate, the Comments column entries should reported as 750814. When a shutdown or significant power reduction begins in one report period and ends in provide identification of each shutdown or significant power reduction that occurs as a direct result of an another, an entry should be made for both report periods to be sure all shutdowns or significant power abnormal occurrence on which a report has been or will reductions are reported. be submitted. (This information may not be imme- diately evident for all such shutdowns, of course, since further investigation may be required to ascertain TYPE whether or not an abnormal occurrence was involved.)

When a direct correlation can be made between a given Use "F" or "S'" to indicate either "Forced" or shutdown and a specific abnormal occurrence report, the

"Scheduled," respectively, for each shutdown or Comments column entry, should state the abnormal signific.ant power reduction. Forced shutdowns include occurrence report number and date.

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

SUMMARY INSTRUCTIONS

'Note that this differs from the Edison Electric Institute (EEl)

definitions of "Forced Partial Outage" and "Scheduled Partial Write a brief summary (i.e., 3 to 4 sentences)

Outage." For these terms, EEl uscs a change of 30 MW as the break point. For larger power reactors, 30 MW is too small a description of the highlights of operation of the unit for change to %%arrantexplanation. the reporting month.

1.16-E-2