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4-c' Pe ius se DIRECTORATE OF REGULATORY STANDAHDS REGULATORY GUIDE 1.16 rREPORTING OF OPERATING INFORMATION-APPENDIX A
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TECHNICAL SPECIFICATIONS
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.J A. INTRODUCTION addressees and designation of the number of copies re-quired, is included in Regulatory Guide 10.1,"Comptla-Section 50.36, " Technical Specifications." of 10 tion of Reporting Requirements for Persons Subject to CFR Part 50, "Licensmg of Production and Utdizatiori AEC Regulations," and is not presented herein.
Facilities," requires that each applicant for a license authorizing operation of a nuclear power plant include m its application proposed technical specifications.
B. DISCUSSION These technical specincations, as issued by the AEC, are incorporated.nto the facility license and are conditions in September 1974 the Regulatory staff published of the license. Technical speciqcations are now included Revision 2 of Regule:y Guide 1.16. This revision re-as two appendices to the licen:ee: Appendix A technical Hected results of a Raulatory staff review of operating specifications relate to health and safety, and Appendix information needed to permit assessment by the Com-B technical specincations relate to environmental im-mission of safety-related activities during the operating pac t.'
Each of these appet. dices includes a section on phase of plant life. Swificant differences in this guide reporting requireme.ts. The reporting program descnbed from Revision I of Re:ulatory Guide 1.16, dated Octo-in tius regulatory guide involves the reporting require-
'ver 1973,were:
ments of Appendix A technical specifications only. In 1.
Reporting requir-c.ents were updated to reDect some cases, this program may need to be supplemented changes in reports required by Appendix A technical or modi 0ed because of unique plant desp features or specifications. In generJ. these changes involved:
other factors. The need for a supplemental or modified a change in n.quency of submittal of routine a.
program will be determined on a case-by-case basis.
operating reports; Reporting of information concerning radioactive b.
elimination of the first-year optrating report; discharges, radiological environmental monitoring, and c.
formalization of reporting of operating infor-nonradiological environmental surveillance and environ-mation on a monthly f-luency; mental impact is discussed in Regulatory Guide 4.8, d.
deletion of certain items of information no
" Environmental Technical Specifications for Nuclear longer required by the iEC to be submitted on a routme Power Plants."
basis; in addition to the reporting requirements necessary e.
changes in the format and immediacy of re-for compliance with technical speci0 cations, specific porting required for mrtain 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 gum nce concerning definitions and Regulations. A compilation of all reporting requirements categories of significai.. of abnormal occurrences.
applicable to the various types of AEC licensees, in-2.
Appendices B, C. :, and E were added to provide
)
ciudmg identification of the proper AEC addressee or the desired format fe radiation expowre reports and monthly operating reports.
3.
A listing of repo:s other than those required by
' A few facihties have a single appendis that contains the Appendix A techmcal eccifications was eliminated.(See combined aspect of Appendices A and B.
Introduction above.)
USAEC REGUL.AToRY GUlOES coo. of pubhshed guida may to covemed by reount moicat.ng t*e d..s.ons desered to the US. Atomic E nergy Cornmessson. Westwagton. Of. 20545.
Roguestory Guedes at asued to descree and meet auslab.e to the pube.c A tt ent ion - Director of Regu6atory standards. Comtrents and sewntoons for nwrovernents on inese guedes are encourspd and should be seet to me Secretary methods accootaase to the AEC Registury sieff of emowmenteng specific parts of e
of the Commiss.on. US. A torme E nergy Comenession. vvashmgton. of. 20545, the Commes.cn's repiations. to denneste tee' niques e4 Dy me staff en A tten tion. Docnetmg and service Section.
even stme soecibe orce6 ems or postuisted accidents, or to provide guidance to u
aconcants. Reguietory Guedes are not substitutes for regu&ations and cornohana oveen them s nos requered. Methods sad solutions different froen t%cte set out m The peces are ensued in tne sono. wing ten broad devis.ons:
tre guides onH be acmorabee of they provede a bases for the hadings requesete to the uswance or com nuance of a permei or hcense by the Commeseen.
- 1. Povver Reactors
- 6. Products
- 2. Research and Test Reactors
- 7. Transoortation
- 3. Fuets and Materials Facihteen
- 8. Occuoetionsa Heatth
- 9. Antitr st Review, a Environmensae and s.tmg Pubisshed guades vesH be revned cereo cally. as sopropriate. to accornmodate u
cornments and to ref 4 SCI note informetson or esperoence
- s. Materiais and Plant Protection
- 10. Geneese gMqpygy g 7 r pa U JE.,. %g 390032
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he mciuded it, t 's o t ne,r' t ? " etc s'iV1ted withm 60 day of puhht.i.
sc! mi. Add lit,rui specific ut
< onnito ns b.ned on the m os kcu "n ;
~r tne in coroun twi.,uh uly
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'evision of the guide. As a result of comunents recelWd to..mn.alde iMai.H os y );uldet.....
.'d ac m.iuded on 'he guide and additional staff review,the Replaorv m m icpor t.
>ta.f has developed Revision 3 to Regulatory Guide St rtup icports >hould be aitteJ withm (!)
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40 3.ws toilowm completion of 'he startup test Significant differences in thn guide from Revision 2 pimeram.12i 90 days followmg sesamption or com.
of Reculatorv Guide 1.16. dated September 1974. are
- m. mement 4 "emd power operation, or (3) 9 1.
The startup report was revised to be more specitic as mouths toituwua nno.n cimcahty, whichever is earbcst.
to the test results to be reported.
If the $tartup Report does not coser all three events 2.
The annual report section was revised to(l) 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 pm.armance.
hase 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.2.3 gram, or f:icsimde transmission of the types of abnormal occurrences listed under Section 2.a. (2) be more
' Reutine 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 re! eases from Appendtx A be submitted prior to Erch I of each year. The initial technical specification reporting requirements, (4) pro-report should be submitted prior to March I 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 Revi en 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 expenence gained dunng the year.
though some repetition of previously reported even in addition to the applicable reporting requirements information may be involved. References in the :mnual of Title 10, Code of Federal Regulations, the icllowing operating rep ~t to previously submitted reports simuld program for reporting of operatinginformation provides be, lear.
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)(c) below.
unless otherwise noted.
(2) For each outage or forced reduction in power
- of over 20 percent of design power level where 1.
Routine Reports the reduction exteads 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 equipmen malfunction);
A summary report of plant startup and power escalation testing should be submitted following (1) receipt of an operating hcense, (2) amendment to the lice.1se involving a planned increase in power level. (3) 8 A single submittal may be made for a multiple umt 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 (4j common to all units at the station.
modifications that may have significantly altered the
$Much of the mformaison tn the Annual Report was nuclear. thermal, or hydraulic performance of the plant.
previously submitted m a Sernunnual Report.
- The term " force <1 reduction m power" as ued m this guide The report should address each of the testsidentified in nd as n rmally detmed in the electne p wer industry means the
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the FSAR and should in generalinclude a description of CCurrenCC I a C mponent failure or other condition wl.ich the measured values of the operating conditions or requues that the load on the urut be reduced for corrective characteristics obtained dunng the test program and a acuon immediately or up to and mcluding the very next week-comparison of these values with design predictions and end. Note that routme preventive mamtenance survedlance, and specifications. Any corrective actions that were required calibration activities requirmg power reducuons are not covered to obtain, satisfactory operation should also be de-by this section.
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5 Ins a bnei disenmun m o reierence to 4 nisce iu.orne no later than tire ternii -
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me or power re.iuctiom (c) correctise action taken to reduce the 2.
Abnormal Occurrene piubabthty of recurrence.if appropnate, (d) operating time lost as a result of the Licensees are required to imntiate and eniuate outage or power reduction (for scheduled or forced the significance of abnormal occurrences arJ impicment i
ou tages.s use the generator offline hours: for forced corrective actions to prevent recurrence. n accordance reductions in power, use the approximate duration of with provisions of techmcal specification. and the pro-operation at reduced power);
gram for quality assurance durmg the operational phase (e) a description of major safety-related of plant life. In addition, abnormal occurrences in-j corrective maintenance performed during the outMe or ciuding corrective actions and measures ;. prevent reoc.
power reduction, including the system and component currerice, should be reported to the AEC as described involved and identification of the critical p2th activity below.
dictating the length of the outage or power reduction; In general, the importance of an occurrence md with respect to safety significance detennines 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 ofits occunence. In such cases the AEC should cent of the allowable annual values.
be informe'd promptly of an increased significance in the (3) A tabulation on an annual basis of the licensee's assessment of the event. In addinon, supple-number of station, utility, and other personnel (in-mental reports may be required to fully desenbe final cluding contractors) receiving exposures creater 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
,,-ms au wum anu joo nuncuans, es., 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 main te-that snould 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 estnates based i
on pocket desiriterer, TLD, or film badge mesurements.
Prompt Notification With Written Followup.
a.
Small exposures totalling less than 20 perant of the i
Meidual 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 ho'urs by telephone and confirmed by telegraph., mail-l to specific major work functions.Se e Appendix B to this gram, or facsimile transmission to the Director of the guide for a standarl format for providing this infor-appropriate Regulatory Operations Regional Office, or mation.
his designate, no later than the first working day fol-j (4) Indications of failed fuel resa.' ting from lowing the event, with a written followup report within
_ j irradiated fuel examimions, including eddy current two weeks. The written followup report should include, p !
tests, ultrasonic tests, or visual examinations.ompleted as a minimum, a completed copy of the licensee event durmg 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 Repd.
formation concerning licensee events. (Instructions for completing these license event report forms are issued 7
Routine reports of operating statistn and shut-individually ' event report form should be supplem to each licensee.)lnformation provided on down experience should be submitted on 2 monthly the licensee basts. The report formats set forth in Appedces C, D, as needed, by additional narrative material to provile.
and E to this guide should be completed in acordance with the instructions provided. The comp!:ted forms complete explanstion of the circumstances surroumimg the event.
should be sent to the Director of Regulatory Operations, (1) Failure of the reactor protection <vstem or U.S. Atomic Energy Commission, Washington, D.C.
other systems subject to limitmg safety-system settings 20545, with a copy to the apprc,pnate RO Regional to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as sThe term." forced outage" as used m this guide and as the limi:ing safety-system setting in the technical specifi-normally defined in the electnc power industry means the occur-cations or failure to complete the required protective rence of a component failure or other condiuon which requires that the urut be removed from service for correcove accon immediately or up to and including the very next weekend.
- 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.
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S :.ctim l'v tollowing are cumpl v 91.00: :r catculated reactivity balance indicating a Shut.
e
'i B e n t or pr.w ire c wed s hmitine d.m n mem lew con'ervative than spumed in the tech.
Oty+. mn setung value without automaus trip.
w..I w u a ar v % > hurt term ra.t..13 uarea3o h th e Inability to % r.J murt suf fic:ent covietoitd to a reactor penod of kn than 5 seconds or.
wntrol rods to achtete the tei.hmaa! s: ecification shut-if sub.anical. an unplanned reactivity insertion of more down margm.
than 50c.or occuitence of any unplaimed ulticality.
(c) failure os the rc ctor protective sys-(5) 1 ailure or malfunction of one or more tem to complete the required protemve action once components which prevents or could prevent, by itself.
imtiated.
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 fuelline(s) resulting in failure able under items 2.a(5),2.a(6), or 2.b(1) below.
to supply fuel to the emergency generator (b) Multiple instrument drift resuhing il (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 cca-condition for operation is less conservative than the least tinue running once initiated.
conservative aspect of the limiting condition fu open-(6) Per onnel error or procedural iradequacy tion established in the technical specifications. The which prevents or could prevent, by itself, the fulfdi-followmg are examples:
ment of the functional requirements of systerns required (a) Shutdown not begun within the speci-to cope with accidents analyzed in the SAR. The foi-fled 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 ir cor-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 "evented injectan on demrd.
(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 redundan.:y (d) System cooldown at a rate exceeding thtt 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 hsted in the technical specifications, the plant shutdown, operation of safety systems, or other limiting condition for operation is not considered to protective menures required by technical specifications.
have been violated and need not be reported under this The following are examples:
item, but it may be reportable underitem 2.b(!; below.
(a) Threatened civil disturbances requirmg 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 sansient or _.ci-(a) Through wall failure of piping or com-dent analyses or in the methods used for such ant's so as ponents of the reactor coolant pressure boundary.
described in the safety analysis report or in the base, ror (b) Steam generator tube thinning in the technical specifications that have or could have ur-excess of acceptance limits in Regulatory Guide 1.83, mitted reactor operation in a manner less conserv ave
" Inservice Inspection of Pressurtzed Water Reactor than assumed in the analyses. The followmg are e.um-Steam Generator Tubes.
ples:
(c) Welding or material defects greater (a) Loss of condenser vacuum resulting in than those allowabic by applicable codes.
reactor pressure and flux transients that peak at values higher than analyzed.
Note: Leakage of valve packing or gaskets withm the (b) Reactivity inser' ion 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.
i (9) Performance of structures, systems or (4) Reactivity anomalies involving disagree-components that requires remedial action or corrective j
ment with the predicted value of reagtivity balance measures to prevent operation in a mannerless conserva-under steady state conditions greater than or equal to tive than that a:sumed in the acc. dent analyses m the O
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wiety analysis report or technical speuniunons bases;or graded mude permitted by a hnutny conoinon for dur'i"; p rit hfe of conditions noi specifically operaia.n. or plan' hutdown ropod '.y : hmuin; t
. o. c w ~'. t b.
tafety analym m mn or f ahmeal
. miu m foi ope-....n. Tin fo:ior r m:;4e-cit i. aison s that require remed:d A"
" co:re.use o n a 'o,e pray punm ine o inpned auer m! to !w Jace mmutes dunn mt. Tnp umt "
m 4.wawso to present the existence c.r devclapment of an unsafe condition. The followmg are exampler me. declared mureraisie and recana.
(a) Axial flux ratios less conservative than (b) Salety injection pump ided to stan those for which correlanons with userpower /.T were tollowmg system ininanon. Re i m..a.e:!!= e an a
based on core burnup projections.
redundant components was successfully c"mpleted.
(b) Failure of a safety injection pump to (c) One of t!= tv.o m.'._.
deliver the flow rates assumed in the FSAR.
pumps became inoperable because of a f aulty bearmg.
(c) Degradation of hydraulic shock sup-Redundant pump operability was confirmed.
pre; sors to the extent that they could not perform their required safety function.
Note: Routine surveillance testmg, mstrument c. libra-(d) Failure of magnetic trip mechanisms tion, or preventive maintenace which require system on a safety-related circuit breaker to provide trip on contigurations as described in items 2.b(I) and 2.b(2) instantaneous overcurrent as indicated on tne manufac.
reed not be reported except where test results them-turer's time-curret characteristic curve, selves reveal a degraded mode as described above.
(c.
4ilure of a safety / relief valve to close after pressure has reduced below the required rescat (3) Observed inadequacies in the implementa-valve.
tion of administrative or procedural controls which (ffThermal 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 followmg are examples:
(a) One of the three diesel generators Note: This item is intended to provide for reporting of tripped from high temperature because coolmg water potentially generic problems.
valves were lined up incorrectly.
(b) Isolation valve for a low-pressure trip b.
Thirty-Day Written Reports.
.a:h ' m f~.-- !.bsmi with system pressure locked in.
Trip of switch wodd na occur at low pressure. Im-The abnormal occurrences discussed below have proper return to operation following maintenance was lesser umediate importance than those described under the cause.
2.a abose. Such everts shou'd be the subject of wntten (c) Failure to perform surveillance tests at t~
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 deig.:d to minman, a completed copy of the licensee event report contain radioactive material resulting from the fission form bee 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.
concermng licensee events. (Instructions for completing these Lensee event report forms' are issued individually Note: Scaled sources or calibration sources are not in-to each licensee.) Information'provided on the licensee cluded under this item. Leakage of valve packing or event report form s..nuld be supplemented, as needed, gaskets within the limits for identified leakage set fcc by adattional narrative material to provide complete in technical specifications need not be reported rnder expl.:. -ion of the circumstances surrounding the event.
this item.
(1) Reactor protection system or engineered safet) :cature instrument settings which are found to be 3.
Unique Reporting Reauirements less centervative than those established by the technical specifications but which do not prevent the fulfillment The above reporti c program wtll in general satisfy of the functional requirements of affected systems.The the reporting requirements necessary for compliance followmg are examples:
with Appendix A technical specifications. This program (a) Ore of the four sc am dump voNme may need to be supplemented or modified because of level su:tches failed to operate during t'rvetllance 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 freauently of 1.16-5 s
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i he time allowed hipi puis uiterest. While some of the events may not if the time for repair is likely to euert t
ric..epon 4 file by regu.atm oi.. ained m other part o; by the techmeal y <is~a.aions tia. guide, die Director the appropnate Regipal e
Office, or his designate, should be informed of such D. IMPLEMENTATIOfJ esents by telephone as soon as possible after the esent has been discovered.
The purpose of this section is to provide mforma-tion tc applicants and licensees regardmg the Regulatory 3.
An event that causes damage to proper.y or staff's plans for utiliimg 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 attemative 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.
Nr.tural 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.r(7) abe e.
Appendix B environmental technical specifications, it d.
Discovery of signincant radiological event off-may be necessary to include those reports identified in site occurring during transport of material for which the Regulatory Guide 1.21, "!!easuring, Evaluating, and licensn was either shipper or consignee.
Reporting Radioactivity in Salid 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 <ooled 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 requnements section of the technical specifi-ment which need not be reported under item 2.a above, cations.
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APPENDIX A 1.lCENSEE EV"'!T l.EI'OttT
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Acre ve TV CONTENT RELEASED OF RELE ASE AwoweT OF ACTIVITv Location op mELE ASE Q
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10 tt 44 45 80 PERSONNEL ExpOSUEES Nuu sE m Tvrt DE sc al* TION l l l
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i MI 9 11 12 13 80 PERSONNEL INJURIES MUMSE R otsc hapt loM l l l l l
7 C9 51 12 go OF FSITE CONSEOUENCES I
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1.16-A 1 390038
STANDARD FORMAT FOR REPORTING NUMBER OF PERSON APPENDIX B I
Number of Personnel (> 100 rnrem)
NEL AND MAN-REM BY WORK AND JOB Woik & Job Function I
(w)
Reactor Operations & Surveillante Utility Employees Contract Workers Total Man-Rem Station I'mployee s
l a'
Maintenance Personnel and Others Station Employee Contract boii7e7 Operating Personnel
~
Utdie Employces s
ami utlicii
~
llcalth Physies Personnel n
U Superviwry Perwnnel bca fi Engineering PersonncI i
\\
Routine Maintenance L_ W /,
3 Maintenance Personnel J..___>
Operating Perwnnel yy
}
llealth Physics Peronnel l'~,
J Sulwrviwry Permnnel
,.:" y Engancering Personnel inservice inspection
, _ _.a L,
Maintenance Personnel Operating Personnel Ilealth Physics Personnel Supervisory Personnel
(
Engineering Personnel e6 Special Maintenance Maintenance Personnel Operating Perwnnel llcalth Physics Personnel Supervisory Perwunca l'nguicering Personnel Wasse Processing Maintenance Personnel Operating Perx>nnel llealth Physics Permnnel Sulevimry Personnel Engineering Personnel
)
i Maintenant c Permnnel Operating Personnel Ileahh Physies Personne)
Supervisory Perwnnel Engineering Personnel y
TOTAL pX Maintenance Personnci C
Operating Perwnnel O
llealth Physics Permanel Supervimry Personnel (jf.
f ngmecting Peswnnel 4
Grand Total
-~-
J i
APPENDlX C DOCK ET.No. __._
UN IT _ __. __
DATE COMPLETED BY N
AVERAGE DAILY UNIT POWER LEVEL s
MONTH AVERAGE DAILY POWER LEVEL AVER..GE DAILY POWER LEVEL DAY (MWe-net)
DAY (MWe-net) 1 17 2
18 3
~
19 4
20 5
21 6
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 Compue to the nearest whole megawatt.On this form, list the average daily unit These figures will be used to plot a graph for each reporting month. Note that by us dependable capacity for the net electrical rating of the unit, there may be occasions whe 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.
1.16-C-!
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APPENDlX D
.I_
D Gi COMPLL i LD bY DOCK F T NO __ _ _
OPER ATING STATUS 1.
REPORTING PERIOD:
TilROUGH _ _,,
HOURS IN REPGRTING PERIOD:
2.
CURRENTLY AUTHORIZED POWER LEVEL (MWth)
MAX. DEPEND ABLE CAPACITY Mw -NET) e 3.
LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED (IF /,NY)iMWe. NET):
4 REASONS FOR RESTRICTION (IF ANY):
THIS CUMULATIVE REPORTING PERIOD YR TO DATE TO DATE 5.
HOURS R EACTOR WAS CRITICAL.
t 6
REACTOR RESERVE SHUTDONN HOURS i
7 HOURS GENERATOR ON LINE.
8 UNIT RESERVE SHUTDOWN HOURS 9.
GROSS THERM AL ENERGY GENERATED (MWH) 10 GROSS ELECTRICAL ENERGY GENEP. ATED (MWH) 11.
NET ELECTRICAL LNERGY GENER ATED (MWH) 12.
RLACTOR AVAILABILITY F ACTOR (I) 1.1 UNIT AVAILABILITY F ACTOR (2) 14.
UNIT CAPACITY l-ACTOR (3) 15 UNIT FORCED OUTAGE RATE (4).
16.
SHUTDOWNS SCHEDULED TO BEGIN IN NEXT 6 MONTHS (STATE TYl'E.DATE. AND DUR ATION OF EACH):
f 17.
IF SHUT DOWN AT ENDOF REPORT PERIOD. ESTIMATED DATE OF STARTUP:
1 is UNITS IN TEST STATUS (PR!On TO COMMERCIAL OPER ATION) REPORT THE FOLLOWINE DATE LAST DATE l
FORECAST ACHIEVED INITI A L CRITIC ALITY INITI AL ELECTRIC \\L POWER GENERATION COMM ERCIA L OPE R ATION (1
REACTOR AVAILABILITY FACTOR
=
X 100 HOURS IN REPORTING PERIOD (2)
UNIT AVAILABILITY FACTOR
=
X 100 HOURS IN REPORTING PERIOD (3)
UNIT CAPACITY FACTOR
=
MAX. DEPENDABLE CAPACITY (MWe-NET) X HOURS IN REPORTING PERIOD
^
(4)
UNIT FORCED OUTAGE R ATE
=
X 100 HOURS GENER ATOR ON LINE + FORCED OUTAGE HOURS h
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INSTRUCTIONS FOR COMPLETING OPERATING DATA REPORT (APPENDIX D)
This report is to be turmshed each month by hcensees.
- 8. Umt Reserve Shutdown lla v W duraticr, m The name, telephone number and extension of the hours that the unit was removed f m service for preparer should be provided in the space labeled economic or samtlar reasons, but was available for T ampleted By."The mstructions below are provided to operstmn.
assist licensees m reportmg the data consistent.'y. The 910. Self Explanatory numbenng of the instruction matches that used on the report format.
- 11. Negative numbers should be used,if applicable.
1215. For units still in the startup and power ascension test phase, items 12-15 should not be computed.
Instead, enter N/A in the current month column. These OPERATING STATUS four factors should be computed startmg 4 the time the unit is declared to be in commercial operation. The
- 1. Reportmg Period. The Period normally will be from 0001 of the first day through 2400 of the last day cumulauve 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. Howe,er, units already in commercial operation, for which eumulauve Ggures have been based on indicate when such vanations occur. Successive monthly different starting dates, need not recalculate the reports should be consistent; i.e., no gaps in tim e.
Report as hour, year, month, day using 24. hour cleck cumulauve hgures.
(000!, 750814 for 12:01 a.m. on August 14. 1973).
- 12. Reactor Availabihty Factor. Compute by Hours in reporting pened should be calculated from divtding Heurs Keactor was Critical (ltem 5) by Hours m report penod.
Report Penod (from item 1). Express as percent, to
- 2. Fer the " net" figure, use Maximum Dependable nearest tenth of a percent. Dunng months when the umt Capacity. Maximum Dependable Capacity is deGned as is shut dow n for the enure penod due to non-reactor the dependable m:un.umt capacity, wmter or summer, Problems, enter "Not Applic'able " Do not inc:ude whichever is smaller.
reserve shutdown hours in the calculation.
- 3. Note that this item is applicable only if
- 13. Umt Availability Factor. Compute by dividmg restnctions on the power level are in effectrShort. term H urs Generator On Line (Item 7) by Hours in Report (less than one month) Itmitations on power level need Penod (trom item 1). Express as percent, to nearest not be presented in this item, smce one of the important tenth of a percent. Do not melude re.erve shutdown purposes of the item is to determine if, and at what haurs in the calculation.
power level, a restricted power level line should be
- 14. Umt Capacity Factor. Compute by dividing Net drawn on the chart of average daily reactor power.
Electrical Energy Generated (item 11) by the product of Since this information is used to develop Ggures Maximum Dependable Capacity (MWe. net) (Item 2) on capacity lost due to restnctions and because most times Houn m Report Penod (fium ltem 1). Express as users of the " Operating P! ant Status Report" are percent, to.he nearest tenth of a percent.
pnmarily interested in energy actually fed to the distnbution system, we request that this figure be d Lim Forced Outage Rate. Compute by dividing Total Fv cd Outage Huurs (from shutdown table, expressed in MWe (net) in spite of the fact that that Ogure must be denved from MWth or percent power.
Appendix L) by the sum of Hours Generator On Line (item 7) ;..s Total Forced Outage Hours (Aopendix 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. Bnef narrative is acceptable. Cit references as appropriate. Irjicate whether restnctions
- 16. Shatdowns Scheduled to Beg n m Next 6 g
are self. imposed or are regulatory requirements. Be as specific as possible withm space limitations. Plants in proposed date of start of shutdown and proposed length startup and power ascension test phase should be of shutdown. It is recogmeed that shutdowns may be identified here.
scheduled between reports and that this item may not be all inclusive Be as accurate as possible as of the date the
- 5. Self Explanatory report is prepaied.
- 6. Reactor Reserve Shutdown Hours. The duration
- 17. Self Explanatory.
in hours that the reactor was removed from service for administrative or other reasons but was available for
- 18. Self Explanatory. Note, 1 : 'ever. that this operation.
inf rmati n is requested for all u ~s in startup and power ascension test status, and is not required for umts
- 7. Self Explanatory already m comn ercial operation.
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APPENDIX E DOCK ET NO. ____._
UNIT SHUTDOWNS UNIT N AM ii _ ___ ___..
DNIl.____.__
~
COMPLiiTl!D !!Y REPORT MONTil
('
)
rD TYPE METHOD OF I,
F FORCED DURATION SHUTTING DOWN f
{cij-g (a)
NO.
DATE S SCHEDULED (HOURS)
REASON (U THE REACTOR (2)
CORRECTIVE ACTIONS /COMMI.NTS N {.
,}
EED i
n F?
IlsRtASON 12 e 414 I lit sii A t QUIPMEN T I All.URI (1.XPt...lNs i M ant il B MAINT.OR ILSI J MANIAl C Rt l L'LIING S( It A Al D-RLGl1LATORY RESTRICTION 4 Atlo'lillr L OPI RA10R TR AINING AND St R A \\1 I trl NSI i XAMINAllON
/
I - ADMINIST R/ ~.!
8 G OPIit A llON AL t RROR l
la XPt AIN) i 11 Ollit k tt Nt'l AINI I
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SUMMARY
INSTRUCTIONS FOR COMPLETING MONTHLY UNIT SHUTDOWN Ri PORTS (APPENDIX E)
>ume ju4 ment is required :-
It is accognved that UNIT SHUTDOWNS estegonzing shutdownf in this way les pencrai. a forced shutdown is one that would not have been completed m This section should descrbe all plant shutdowns the absense of the condition for which corre6uve astion during the report period. In addmon, it should be the source et e planation of significant dips in average was taken.
power levels (Appendtx C). Each sigmficant reduction in power level (greater than 20% reducuan m average daily DURATION (HOURS) powr.r 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 sh :tdown extends beyond completely. For such reductions in power level, the the end of a report penod, count only the time to the shutdown duratien should be zero, the method of end of the report penod and pick up the ensuing shuttmg down the reactor should be N/A, and the down ume in the followmg report periods. Report Comments column should explain. The Comments duranon of outages or sigmficant reducuons m power column should be used to provide any needed rounded to the nearest tenth of an hour to facthtate explanation not adequately descnbed by the coded summanon.
columns. Please do not add to the I tt of codes or legends now fumished. Simda 'v, do not add additional columns.
REASON a.
Categorize by letter designation in accordance with the table appeanng on the report form. If none of the NUMBER specificj categones can be used, supply bnef comments.
This column should indicate the sequential number assigned to each shutdown or sigr.iiicant reduction in METHOD OF SilbTTING DOWN THE REACTOR power for that calendar year. V.Len a shudown or significant power reduction begins m one report period Categorize by number c'.esipation m acconcance and ends in another, an entry shoWd be made for"both with the table appearing on the report form. If none of report periods to be sure all shutdowns or significant the specified categories can be used, supply brief power reductions are reported.
comments.
DATE CORRECTIVE ACTIONS / COMMENTS This column should indicate the date of the start of each shutdown or sigmficant power reduction. Report as Use this column to amplify or explain as necessary.
year, month, and day. August 14i 1975 would be appropriate, the Comments column entries should reported as 750814. When a shutdown or significant provide identification of each shutdown or significant power reduction begns in'one rep-- period and ends in power reduction that occurs as a direct result of an another, an entry should be r.- Je for both report abnormal occurrence on which a report has been or will penods to be sure all shutdown. or sigmficant power be submitted. (This information may not be imme.
reductions are reported, diately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or not an abnormal occurrence was involved.)
TYPE When a direct correlation can be made between a sven shutdown and a specific abnormal occurrence report, the Use "F" or "S" to indicate either " Forced" or C mments column entry, should state the abnormal
" Scheduled," respecuvely, for each shutdown or occurrence report number and date.
sigmf. cant power reduction. Forced shutdowns include those required to be initiated by no later than the weekend followmg discovery of an off. normal condinon.
SUMMARY
INSTRUCTIONS
' Note that this dsffers from the Edison Electne Institute (eel definit ons of "I'orced Partial Outage" and " Scheduled Partial Wnte a brief summary (i.e., 3 to 4 sentences)
Outage. For these terms. eel uses a shange of 30 MW as the descnption of the highlights of operation of the unit for bseak point. For larger power reactors. 30 MW is too small a the reporting month.
change to w arrant esplanation.
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LDuring inseection following r::aintenance activity at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />. +cr I
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mI water leakage was observed at the interface between the reactor vessel andI 1 F-2 rod drive housing. No leakage was noted at any other similar housing 1 o
interface.
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Shutdown concition was established pending evaluation. No I
L prior leakage at housing has been observed. No hezard to the ou'lic e
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Reportable per Tech. Spec. 6.9.2.a.(3)
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a Attach =ent to LER-79-018-01T-0 Consumers Power Co Big Rock f oint Plant Docket 50-155 Following replacement of "o ring" seals on four control rod drive flanges, an inspectics with primary system pressure at 900 psig and the reactor suberitical revealed water on the outside of the drive housing at F-2 at 0406 hours0.0047 days <br />0.113 hours <br />6.712963e-4 weeks <br />1.54483e-4 months <br /> on 4-20-79.
Since this could not pos-itively be attributed to condensation, reactor vessel ther=al insula-tion was removed and water was observed to be coming from the shrink fit interface oetween the reactor vessel and the F-2 drive housing with the primary systen pressure at 500 psig at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on 4-20-79.
The leak rate average over a four hour period at about 900 psig was 8.7 mill 111ters per minute. When reactor pressure was reduced to atmospheric conditions, the leakage stopped.
The plant remains in shutdown condition pending identific : tion of the exact leak mechanism and subsequent evaluation. A project group has been organized to investigate the problem and the Nuclear Steam Supply System vendor and the reactor vessel fabricator have been contacted for assistance.
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2 I Durine routine ve-kiv testi c. the e -ere-rev dies.1 e-na--ts, eyep 4-I m ; voltage remained at zero.
'~he e=ergency bus was being supplied by the t
normal source and no hazard occurred.
The unit is not required during l
, i gI shutdown conditions and was returned to service follevine ecerletien of I
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7 I torted in our letters of 10-8 70 and 0-18-72.
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The unit tested satisfactorily on 1
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Subsecuent week'vt yi tests have been satisfactory.
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.4 EVENT oESCRIPTioN ANo pro 8ABLE CoNSEcu!NCES h o 2 1 During routine control rod drive scram timing tests, Drive A-2 scrar ed in I gi 6.0 seconds thus exceeding the limit of 2.5 seconds for 90* insertion in i
l T/S 5.2.2(a)ii. Scram timing on all other drives was normal; thus no unduei o.
h g i azard occurred.
Incident repetitive and similar to event reported as RO-m 78-43.
Plant was in shutdown condition and procurement of parts for the g
g g solenoid valves (ASCo 831622-HVA-90-441-1A) was expedited as outlined be-g 10V-o. i I
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lTTin i nvestigation revealed that the Buna-N disc on the moving cor+. of one of g
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,tlement, resulting in slow venting action.
Parts were replaced in all 73 g scram & dump tank solenoid valves & retesting was satisfactory on 10/30/78.,
A preventive maintenance program will be established to prevent recurrence.;
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BIG ROCK P0riT NRC PORM 364 U.S. NUCLE AR R ECULAToRY Coh4MISSloN (7 77)
LICENSEE EVENT REPORT 1
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(PLEASE PRINT om TYPE ALL REculRED INFORMATioN)
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g iDuring reviews associated with the Svstematic Evaluation Program, solice I
gmaterials used in control and instrumentation circuits for equip =ent re-I o 3 g Iquired to operate during a postulated LOCA were deemed to be marginal in 1
o 3 imoisture resistance characteristics.
The plant was in shutdown condition att io_1tLI l_the time of this eval 2ation and thus no hazard to the public cccurred.
Re-I gportable based on Technical Specification 6.9.2.a.(9).
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gprovide adequate moisture proofing integrity.
Thus, the possibility of cir-1 g lcuit failure due to grounding or hot shorts existed.
All circuits recuired I m i or LOCA were inspected and repairs completed on 10/31/78.
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[7TT1 IFailure, between 7/26/78 and 8/19/78, of the check valve providing contain g
[TTr1t=ent integrity in the 2" demineralized water line to contain=ent contrib-t
[TT71 luted to radioactive contamination of the plant demineralized water system.
ITTriITwenty-five gallons of this water was removed from the plant by employees.
i o e icontainment integrity was established on 8/21/78 and evaluation on 8/23/78 t
y l revealed that no undue health hazard exists for any employees or the pub-r5Tr1ilie.
Check valve failure is repetitive. See Ro-77-31 dated 8/25/77.
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CAUSE DESCRIPT1oN AND CoRRECnVE ACTIONS 27 The check valve was reoaired on 9/5/78.
Containment integrity had been es-t o
Itablished bv valvine on 8/21/78 when the check valve defect became susoect.I i i I eportability*is based on T/S 6.9.2.b.(2).
Inadequate survey per 10CFR20.-i R
g (201 resulted in unnonitored removal of water from the site and revised ad-l tministrative controls are beine imolemented to prevent recurrence.
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l Local Press Release Issued on 8/23/78 l,3,,1,,,_j 1 l lllll l1iffIIl s
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Attach =ent to IZR 032-011-0 Consu=mrs Power Co Big Rock Point Plant Docket 050-155 Investigation of abnormally high radioactive materials levels in Lake Michigan water samples between 7/26/78 sad 8/19/78 led to the discovery that the samples contained radioactive impurities caused by contamina-tion of the plant demineralized water rupply.
De=ineralized water is used to rinse the sampling hardware.
2; valuation on 8/21/78 established that the 2" containment isolation check valve in the demineralized water supply line to containment was defective and that backflow from the fuel pool system was the source of contamination in the de=ineralized water system.
On 8/21/78, redundant valve cv/blos was closed to isolate the source of contamination and it was verified leak-tight on 8/25/78 fonoving veri-fication on 8/25/78 that the 2" check valve was defective.
Demineralis-ed water taps and lines in the turbine building were closed and/or caution tagged on 8/21/78 and 8/22/78.
An on-site employees were informed of the problem on 8/21/78 and a survey was initiated to determine if urmonitored demineralized water had been used by anyone or re=oved from the plant.
The survey revealed that about 25 ganons of water had been removed frem the site in several containers. Of the fifteen gallons of water retriev-ed, the highest activity was in the order of 100 MPC in one five-ganon container. Evaluation of each unretrievable use determined that no human consu=ption occurred and no undue hazard existed for any e=ployee or the public.
The exact mechanism for cross-contamination is not known but the 2" check valve in the demineralized water supply to the containment has been repaired and tested and the design of the valve vill be reviewed to determine if reliability can be improved.
In addition, ranual valves VSFP-20 and VSFP-27 (one in each of the two fuel pool system connections to the demineralized water system) have been placed under lock control to preclude misoperation.
The removal of contaminated water from the plant is the result of inadequate survey practices. Periodic testing of the demineralized water is now being conducted to detect contamination and radiological clearance p;actice for re= oval of material from the site is being reviewed for possible improvements.
390052