ML19221A847

For Comment Issue of Reg Guide 1.16,Revision 4, Reporting of Operating Info - App a Tech Specs

ML19221A847
Person / Time
Issue date:	08/31/1975
From:	NRC OFFICE OF STANDARDS DEVELOPMENT
To:
References
REGGD-01.016, REGGD-1.016, NUDOCS 7907100088
Download: ML19221A847 (15)

Text

.

Revision 4 U.S. NUCLEA9 REGULATORY COMMISSION August 1975 REGC_ATORY GUD D E OFFICE OF STANDARDS DEVELOPMENT REGULATORY GtMDE 1.16 REPORTING OF OPERATING INFORMATION-APPtiNDIX A TECHNIC AL SPE'.;lFIC ATIONS e

A. INTRODUCTION of Reporting Ree,unements for Persons subject t i NRC Regulat ms," and is not presented herein.

Sec tion 5036, "lechmca! Spectiieations.' of 10

([

CFR Part 50. "Licenwg of Production and Utihzation B. DISCUSSION Facihties.' requires that each apphcant for a heense authon/mg operation of a nudear power plant mciude In Septembtr 104 the Wmic gy Commis-in m epht a tion propo,ed technical specifications.

sion Regulatory staff pubbhe} evisiomt of Regula-2 These v xal 3 :ci6 cations, as issued ty the NRC, are tory Guide 1.16. This reu@G

! results of a staff inc o" d mto toe tacihty hsense and are conditions reuew of eperating pfor%ert eded to permit of th

.e. Technical specifications are now included assessment by the (

mi

'on $afey-related activities as twt apg. dices to the license: Appendix A technnal during the opeutm ase st plant life. Significant s pecific1tiens clate to health and safety, an<i Appendix changes m rem 2 d

unEnents were updated to reflect B technical specub.tions relate to enuronmental im-or pa c t. ' Each of these appendices includes a section on changes *h g @cral, these changes involved:

guired by Appendix A technical sfechatN..M reporting requirements. The reporting program described m this regulatory guide mvolves the reportmg require-change in frequency of submittal of rnents of Appendix A technical specifications only. In guth. ratmg reports; some cases, this program may need to be supplementei VM elimination of the first-year operating or moditied because of unique plant design fea:ures as

%$f othe factors. The need for a supplemental or mom.e ~ gE c.

formalization of reporting of operating program will be determined on a case-by-case basis ![

,information oa a monthly frequency; Reporting of mformation concernin at@Wgj d.

de!ction of cert iitems ofinformation no discharges, radiotopcal environmental m a

longer required to be submitted on a routme basis; it o nn,d on-nonradiological ensironmental survedlanc d cr e.

changes in the format and immediacy of mental impact is discussed in Regulato

' 4.8, reporting requiied for certain types of abnormal occur-

"Ensironmental Technical Specifications for 'udear rences (now called reportable occurrences);and i

Power Plants?

f.

improved guidance concerning definitions in addition to the repMif tequirements necessary and c.tegones of significance of abnor 11 mcurrences.

f for comph= ace with techhbd gepheations, specific re-2.

Appendices were added to proe e the desired portmg requiremenggin%cd 7$ Part 50, as well as format for radiation exposure reports and monthly in other Parts ofEtte t C$ter I, Code of Federal opering reports.

Regulations. $ ctgii3ri.

if ali reporting reqHrements 3.

A hsting of uports other than those required appheable MHhe n$'*6e proper NRC addressee or ad-gs pes of NRC licensees,includ-by Appendix A techmcal specifications was eliminated.

ing identiK;egd of (See introduction above.)

dressees andhgnation of the number of copies requir-ed, is included V Regulatory Guide 10.1, " Compilation 2 ne Atomw rnern commisuon was abobshed by the Energy Reorganizatwn Act of 1974, wtac!: also created the Nuclear I A few facditees have a ungle appenda that contains the Regulatory Comnusuon ari gave it the bcensmg and relatad combmed aspect of Apper. dices A and B.

regulatory functions of the /iC USNRC REGULATORY GUIDFS comments saould be wat to the 5= rett v of the Comm.moa us weer

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aesseto'v Go d*s e e iss-*d 'o dest '+e sad mes e e s 'atue to the puboc method s ar teptetue to the N RC staf f of implemeneing oper.. tic. parts of the Comm.ss.on s se p+at.o as to det neste tec hn. ques used b y the ste*

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cents poh.onal Hesteh m.t h them es not aegw.e d Me, hods sad sotuoons d.f terent f rom sbose set out m 2 pes r h end iest R ee to's 7

e tion U the gwdes em be er r epeeb+e t ther prow de a bas.s toe the find.ngs reqws.te to 3 f uels and Meter.e's iet ibties 8

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c e of a poe m.t or be ease by the Commiss.on the innans e or i o o u.

4 inveeonmented and Siemg 9 Ant. trust Poveew C om ments an.2 so -est ons 8 vr im pr o,em ent s o these guides e e en

• raged b Maver ein and Pient Protect.we 10 G ee=o r el et au omes en a g + oss

.ti he re vised as erprope.ste m ae c ommodaie v om Cou os of put.hshed guides me, be obte ned b, written request

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Cm ments were muted withm 60 days of pubhca.

1.

Routine Reports tn " ot Reusmn 2 f or use in conjunction with early of the puW As a result of comments received a.

Startup Report.

res n on ih _ aide and addulonal staff resiew, the staff dneWeJ Ro mn 3. Sipmicant changes m Rei.. on 3 A summary report of plant startup and power were.

escalation testmg should be subnutted following (1) 1.

The statup report was revised to be more receipt of an operating beense, (2) amendment to the specitic n to the int results to be reported.

heense involsing a planned mercase in power lescl. (3) lk annual report section was revised to (I) installation of fuel that has a ditferent design or has been further quannty the term " reduction in power,' (2) nunufactured by a dif fe ren t fuel suppher, and (4) pwuda f urther guidance on reporting of occupation.d modifications that may base siputicantly alteied the radution exposum and(3) reuse the mformation to be nucl ear, thermal, or hy draulic performanse of the plant.

submeted on fuel pertonnance.

T he report should address each of the tests identified in 1 Ihe abnormal occunence report section w as the FSAR and should m generalinclude a description of ra ned to (1) preside for prompt notification by the measured values of the cperating conditions or anJ wnfirmation of such notification by characteristics obtained during the test program and a telepho s

idegraph. madgram, or facsmu!e transmission of the comparison of these va!ues with design predictions and ty pes et abnomul occurrences listed under Section 2.a, specifications. Any corrective actions that were required (2) be ore specific on the ty pes of abnormal occur-to obtain satisfactory operation should also be de-

. nses reportcJ. t 1) delete radmlopeal ettluent releases senbed. Additional specific detads may be included in from Appenda A technical specification reporting beense conditians based on the appheant's commitment requaements, (4) provide for reporting of the types of to appheable regulatory guides and should be included in abnonna! scurrences listed under Section 2.b wahm 30 this report.

day s of scunense of the esent. and (5) make Section Startup reports should be submitted within (1) ic of Resision 2 of the guide a separate section (Section 40 days following completion of the startup test 41 program, (2) 90 days followmg resumption or com-In prenous rensions of Regulatory Guide '.16. the mencement of commercial power operation, or (3) 9 term " abnormal occurrence" was used to designate any months followmg initul enticahty, whichever is earnest.

unscheduled or unanticipated opeiational event reported if the Startup Report does not cover a!! three events to the fomnuwon. Induded in these reported events (i.e., initial criticahty, completion of startup test pro-gram, and resumpt on or commencement of commercial i

were (1) esents that could or did hase significance from the standpoint of pubhe health or safety and (2) events power ope ration;, supplerrentary reports should be reponed to NRC for performance evaluation and trend submitted at leas, every three months until all threc deternanatmns. In Section 208 of the Energy Reorgam.

events have been comnleted

- atmn Att of 104 (Pub. L 93-438), an " abnormal occun ma ' is defined for the purposes of the reportmg b.

Annual Operating Report.'

, regements ot the Act as an unscheduled incident or esent w hich the Commission determines is significant Routine operating reports cosering the opera-hom the standpo nt of public health or safety. In order tion of the unit during the previous calendar year should to l e consistent with this defimtion, the esents Jesig.

be subnutted prior to March I of each year. The imtul nated in preuous rensions of this guide as " abnormal report should be submitted prior to March I of the year n m unences" are desiputed " reportable occurrences" follow mg im tial en ticality.

m Reuen 4 Any " reportable occurrences" that are Die primary purpose of annual operatmg reports A ' m.med by the Comnussion to be sicnificant from the isto permit annual evaluationby the NRC statiof operat-sonJpomt of pubhc health or safety will be further ing and mamtenance expenence throughout the nuclear

! de wnatcJ "abnornu! occurrencesf power industry. The annual operating reports nude by heensees should provide a comprehensise sununary of "E # *"#* P"#

"8 C. REGULATORY POSITION though some repetition of prenously reported informa-tion may be invohed. References in the annual operatmg hi whtion to the apphcable reportmg requirements repm to premu@ senuued reports should be clear.

luh IR Code of Federal Regulations. the following Each annual operattne report should mclude.

p cr ani lor re j"'rt u:c of operatim' inf.ormation provides

(

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• ""

• O " I. "P#'"3"E"*"'

o ueptan, les ' the NRC' staff for meeting the to ence dunng the report penod relatmg to ute rperation r 7 la c requnements <>f Appendix A technical speciti-

. h, in u ng k

nknance not o

h-Reports sdmitted m accordance with this guide covered in item 1.b ( 2 He) below

,; E addre ned to the Ihrector of. he appropnate t

W Repnal Othce unless otherwise noted.

3 A sm;le submittal may be n.ade for a multiple unit stataan 1 he submittal should mmbine those mtn ns that are mmmon to

• I:

s Mac wimntm ihngn Imm preuous nsue all umts at the station 125 05b l. l b-2

(:l l'or cam a tage or forted reduction in tests, ultrasome tests, or usual nanunations comHm nwer' ot o,er 20 persent ef design power lesel where during the report period euends for mure than four hours:

9 the teJa (a) the p:oximate cause and the system e.

Monthly Operating Report.

and map <. mp..ent 'nsohed (if the outage or forced reduction m powei mwhed equipment malfunction);

Routine reports of operating stanst:a and (b) a t>nef discussion of (or reference to sht.tdown expenente should be submit ed on a monthly reports ot) any reportaNe occurrences pertai: ting to the basis. The report fonuats set forth in Appendices B, C, outage er power redu.nen, and l) to this guide should be completed in accordance (c) correctne action taken to reuoce the with the instructions provided The completed forms probah hty of rat.nence,if appropriate; should be subnutted by the tenth of the month t

(d) operatmg time lost as a result of the foHowing the calendar month cosered by the report to outage or power reducnon (for scheduled or forced out-the Director, Oftice of hgement information and ages) use the generator-off-line hours; for forced r?

Program Control, U.S. Nucleai Regulatory Comnussion.

Justions m power, use the appronmate duranon of oP-Washington, D C. 20555, with a copy to the appropriate eren at reduced power);

NRC Regional Office.

dessuption of major safety-related (c) a wrrettne mamtenara perf ormed dunng the outage or 2.

Reportable Occurrences power reJatmn. mJudmg the system and component mvohed and identuicanon of the entical path aettvity G.. dance concerning reportable occurrences that ui dxtatu.g th; length of the outage or power reduction; should be reported in dif ferent nme frames is provMed below. Supplemental reports may be required to fully

( f) a report of any sm.gfe release of radio-describe final resolution of the occurrence. In cases of.

f actnity m smgle radution exposure specifically assoet, corrected or supplemental rei orts, a bcensee esent ated with the outace wluch accounts for more th.,n 10 report should be completed and reference should be percent of the adowable annual values.

made to the origmal report date.

(M A tabulation on an annual basis of the num ber of stanon, unhty, and other personnel (in-Prompt Notification with Written Followup.

a.

c!udmg wntractors) receismg exposures greater than 100 mrem. > r and their associated man-rem exposure The types of events listed below should be aaordmg to w ork and job functions,* e g.,

reactor reported a., expeditiously as possible, but within 24 9

operanens and suneiU2r.ce, insemce mspection, routine hours by telephone and confirmed by telegraph, mad-maintenance, special maintenance (describe main te.

gram, or facsimile transmission to the Director of the nance). w aste proses 3mg, and refueling. The dose assign.

appropnate NRC Regional Office, or his designee, no ments to sanous duty tunctions may be estimates based later than the first working day followmg the event, with on pocket dosm:eter, TLD, or film b'adge measurements.

a written followup report within two weeks. A copy of Smau expmures tota!!ing less than 20 percent of the the confirmation and the written followup report should indnidual total dose need not be accounted for. In the also be sent to the Director, Office of Management aggregate, at ut 80 percent of the total whole body information and Program Control. USNRC. The written Jose recened m external sources should be assigned to specific major work functions. See Appendix A to foUowup report should include, as a minimum, a completed copy of the licensee event report form (see this guide for a standard format for providing this Appendix E to this guide) used for entering data into the in formanon.

(4) Indications of failed fuel resultmg from NRC's computer. based file of information concernmg hcensee events. (Instructions for completmg these irradiated fuel examinanons, including eddy current licensee event report forms are issued individually to 7

each licensee.) Information provided on the licensee lhe term "ferced redaction tn power" as used tn this guide and event report form should be suEplemented, as needed,

,s as norrnat!> detmed in the electric power industry means the by additional narrative material to provide complete of a component failure or other condirmn that ou urrence requires that the load on the unit be reduced for correctne explanation of the circumstances surroundmg the esent.

ac tion immedutcly or up to and including the very next (1) Failure of the reactor protection system or wtekend Note that routine presentive maintenance, other systems subject to limiting safety-system settine sa n c dla n ce, and cabbration att rvities requirmg power to Imtiate the required protective function by the time a rtJations are not tovered by this section m nitored parameter reaches the setpoint specified as

'The terrn "forted outaye" as used in tbts guide and as norma' y the hmiting safety system setting m the technical specih-J power mdustry means the occurrence of defined m the elect: :

a component failure or "her condition that requues that the

[

unit be removed f rom w.

ce for corrective action tmmediately or up to and meludmg the very next weekend.

7lnstruction Manual, Iicensee taent R eport I tie, Of fite of

• Ttts tabutatmn supplements the requirements of 120.407 of Management information and Program Control. U S N utica r Regulatory Commisson, Washmgton. D C. 20555 in CI'R Part 20 1.16-3 g

cations or fadure to complete the required protective (4) T'eas tiuty anomabes mvolving disagreement function. The followmg are examples?

with the predicted value of reactivity balance under steaJy-state conditions during power operatio (a) Reactor pressure exceeds limiting than or equal to 1" ak/k; a calculated reastnity balance safety-system setting value without automatic Inp.

(b) Inabihty to trip and insert s af0cient indicating a shutdown margm less consenative than control rods to achieve the technical specification shut.

specified in the technical speci0 cations; short term react-Awn margin.

ivity increases that correspond to a icactor period of less (c) Failure of the reactor protective system than 5 seconds or, if subentical, an unplanned reactivity to complete the required protective action once tmti.

tnsertion of mote than 0.5% ak/k;or occunence et any l ate.t.

unplanned cnticality.

(5) Failure or malfunction of one or more tom-Note: Instrument drift discovered as a result of testing ponents which presents or could present, by itself, the need not be reported under this item but may be report.

fulfillment of the functional requuements of system (s) able under items 2.a(5),2.a(6), or 2.b(1) below.

used to cope with accidents analped in the S AR. The followmg are eumples:

(2) Operation of the unit or affected systems (a) riogged fuel hne(s) resulting in failure when aay parameter or operation subject to a hmiting to supply fuel to t..e emergency generators.

condition for operation is less conservative than the leas't (b) Multiple mstrument drif t resultmg in conservative aspect of the hmitmg condition for opere loss of protective function, t2on estabhshed in the technical speci0 cations. The fol.

(c) IIPCI failure to start or faihne to con-lowing are examples:

tmue running once initiated.

(a) Shutdown not begun withm the speci.

(6) Personnel error or pro <edural inadequacy fled time when unidentified reactor coolant leakage ex.

which presents or could prevent, by itself, the fulfill-ceeds the technical specifications hmit.

ment of the functional requirements of systems requued (b) Failure of a system other than the to cope with accidents analped m the SAR. The follow-systems subject to limiting safety-system settings (see ing are c umples:

2.a(1) above) to actuate, or actuation cf such a system (a) Failure to restore a safety system to at a morutored parameter value less conservative than operabihty following test or nuintenance.

that listed in the technical specifications for the system.

(b) Improper procedure leadmg to m-(c) Operation with unacceptable contain.

correct vahe lineup which resulted in closure of one ment leak rate type B or C rest results.

manual vahe m each of two redundant safety mjection (d) System cooldown at a rate exceeding subsy stems and would have presented injection on the technical specifications limit.

demand, Note: If specified action is taken when a system is found Note: For items 2.a(5) and 2.a(6) veduced redundancy to be operating between the most conservative and the that does not result m loss of system function need not least conservative aspects of a hmiting condition for be reported under this section but may be reportable operation hsted in the technical specifications, the under items 2N2) and 2.b(3) below.

limiting condition for operation is not considered to have been violated and need not be reported under this item, but it may be reportable under item 2.b(2) below.

(7) Conditions ansing from natural or man-made events that, as a direct result of the event, require (3) Abnormal degradation discoscred in fuel plant shutdown, operation of safety sy stems, er other cladding, reactor coolant pressure boundary, or primary protectise measures required by technical specifications.

containment.The following are examples:

The foHowine are cump!cs:

(a) Through-wall tailure of piping or com-(a) Threatened cml disturbances reqmnng ponents of the reactor coolant pressure boundary.

plant shutdown (b) Steam generatoi tube ihmning in excess (b) ()amage to the fauhty caused by Gre, of acceptance hmits in Regulatory Guide 1.83, Good, carthquake, or other smular occunences.

"Insenice Inspectmn of Pressurved Water Reactor (8) Enors dncosered m the t ran sien t or Steam Generator Tubes."

accident an aly ses or m the methods used for such (c) Weldmg or material defects greater than analyses as destnbed in the safety analysis report or in those allowable by applicable codes.

the bases for the techmtal specincanons that h.ne or could have permitted reattor operatien m a nunner less Note: Leakage of vahe packing or gaskets within the conservative than assumed in the analpes The followmg hmits for identified leakage set forth in techmcal specifi-are examples cations need not be reported under this item.

(a) l oss of tondenser vn unm resultmg m reactor pressure and flux tranuents that peak at salues b umdes m miended to N inntratoc only.

higher than analped.

1.16-4 125 058

(b) Reactivit y inse rtion delay times by of the functional requnenents of attecied sy stems. The followmg are examples reactor protection system longer than those used in the technical specification bases.

(a) One ut the hiur scum dump mlume N

(9) Performance of structures, sy stems, or com.

lesel smtches failed to operate dunng sanci anse test-ponents that requires remedial action or corrective (b) One ot four reactor h+prewure measures to present operation in a manner less conserva-switches operated at SX5 psig instead of IMS salue of tne than that assumed in the accident analy ses in the o00 psig.

(c) Dunng test, one out of four under-safety analy sis report or technical specifications bases; or diseosery during plant hfe of conditions not siveitically voltage relays failed to perform its tunenon of inpping a considered in the safety analssis report or technical spe-reactor trip breaker.

eifications that iequire remedial action or corrective (2) Conditions leadmg to operation m a de-measures to present the existence or deselopment of an gudeu mode permitted by a linating condition for unsafe condition. The follow'ng are cumples:

operation, or plant shutdown requned by a hmiting condition f or operation. The followmg are examples:

(a) Axial flux ratios less conservative than (a) Core spuy pump breaker tnpred after those for which correlations with overpower.1T were 20 minutes dunng test. Trip unit was found to be based on core bornup projections.

defectise, declared inoperable, and repaned.

(b) Failure of a safety injection pump to (b) Safety injection pump tailed to start dehser the Gow rates assumed in the FSAR.

(c) Degradation of hydraulie shock sup-followmg sy stem initiation. Required suncillance on pressors to the extent that they could not perfom) their redundant components was successfully wmpleted.

(- ) One of the two centnfugal charging required safety function.

(d) Failure of magnetic trip mechanisms pumps became inoperable because of a faulty beanng.

on a safety related circuit breaker to proside trip on Redundant pump operability was conGrmed.

mstantaneous overcurrent as indicated on the manufac-turer's time current characteristic cune.

Note: Routine surveillance testing, instiument cahbra-(e) Failure of a safety / relief valve to close tion, or preventive maintenance which require system atter pressure has reduced below the required rescat con 0gurations as desenbed in items 2.b(1) and 2.b(2) need not be reported except where test results them-v ah e.

(f) Thermal shock to the reactor coolant selves reveal a degraded mode as desenbed above.

system resulting from inadvertent safety injection actua-tion.

(3) Observed inadequacies in the implementa-tion of administrative or procedural controls which Note: This item is intended to provide for reporting of threaten to cause reduction of degree of redundancy potentially generic problems.

provided in reactor protection systems or engineered safety feature systems. The following are examples:

b.

Thirty-Day Written Reports.

(a) One of the three diesel generators tripped from high temperature because cooling water The reportable occurrences d scussed below valves were lined up incorrectly.

should be the subject of written reports to the Director (b) Isolation valve for a low pressure trip of the appropriate NRC Regional Of6ce within 30 days switch was found closed with system pressure locked in.

of occurrence of the event. A copy of the written report Tnp of switch would not occur at low pressu re.

should also be sent to the Director, Of6ce of Manage-Improper retum to operation following maintenance was ment Information and Program Control. The written the cause.

report should include, as a minimum, a completed copy (c) Failure to perform surveillance tests at of the licensee esent report form (see Appendix E to the required fiequency.

this guide) used for entering data into the NRC's computer-based Ole of information concerning licensee (4) Abnormal degradation of systems other events. (Instructions for completing these licensee event than those speciGed in item 2.a(3) above designed to report forns are issued individually to each licensee.)

contain rathoactive material resulting from the fission 7

Information provided on the hcensee event report form process. For example, a through wall leak in a liquid should be supplemented, as needed, by additional narra-waste storage tank.

tise material to provide complete explanation of the cir-cumstances surrounding the event.

Note: Sealed sources or calibration sources are not (1) Reactor protection system or engineered included under this item. leakage of valve packing or safety feature instrument settings which are found to be gaskets within the limits for identiGed leakage set forth less conservative than those established by the technical in technical speci0 cations need not be reported under} specineations but which do not prevent the fulfillment this item. 1.16-5

3. Unique Reporting Requ;rements e. Unscheduled shutdowns expected to last for more than one week, regardless of cause. The above reporting program wdl in general satisfy f. Unusual releases of radioactive material from the reporting requirements necessary for compliance the site boundary not reportable under other require-with Appendix A technical specifications. This program ments. may need to be supplemented or modified because of g. Failure of or damage to safety related equip. unique plant design features or other factors. The need ment which need not be reported under item 2.a above, for a supplemental or modified p ogram will be deter-if the time for repair is likely to exceed the tima allowed mined on a case by-case basis and so designated in by the technical sp:cifications. individual operating liceases. 4. Events of Potential Public Interest D. IMPLEMENTATION The types of events listed below are frequently of The purpose of this section is to provide informa-high public interest. While some of the events may not tien to applicants and licensees regarding the NRC staff's be reportable by regulation or defined in other parts of plans for uti'izing this regulatory guide. this guide, the Director of the appropriate NRC Regional Except in those cases in which the applicant Office, or his designee, should be informed of such proposes an acceptable alternative method, the reporting events by telephone as soon as possible after the event program described herein is being used by the NRC staff has been discovered. in order to standardize the reporting requirements section of Appendix A technical specifications of all a. An event that causes damage to property or operating licenses. equipment when such damage affects the power pro. For licensees holding operating licenses without duction capability of the facility. Appendix B environmental technical specifications, it b. Radiation exposure to licensee personnel or may be necessary to include those reports identified in members of the public in excess of applicable exposure Regulatory Guide 1.21, " Measuring, Evaluating, and lindts set forth in 10 CFR Part 20. Repcrting Radioactivity in Solid Wastes and Releases of c. Natural or man made conditions that may Radioactive Materials in Liquid and Gaseous Effluents requir-action which need not be reported under itera from Light WaterCooled Nuclear Power Plants," and. 2.a(7) above. Regulatory Guide 4.1," Programs for Monitoring Radio-d. Discovery of signiticant radiological event off-activity in the Environs of Nuclear Power Plants,"in the site occurring during transport of naterial for which the technical specifications under the unique reporting licensee was either shipper or consignee. requirements section of the technical specifications. o G 9 125 060 $ 1.16-6

rs t kroe sr N Wht O tO cad I r n T t a n C o N C U F B sc O e y J m lp o e D R m N n E a A M ty i K l l a t ti R o U T OW Y s B eey M o E lp m R I N n o A ita M t S D NA sr L e AN r s k E r o e h Wt XN O t I O ad c DS t a r n n NR o EE C ) PP me P r F A m O 0 s 0 R e 1 ey E o B ( lp M l m enn U m I N r ty e i P l i G t f U N o r I e T b R m s u e O c N y P o E lp R m R t n O o F ita t T S A M ec R n O la F lievr l l l l le D u l le l e l n l l l n l l n l s e e e e l n l l l n l l S l n l l n n l e n e e n l s e e n e e R l n l l e n l s nn i onr n onr onr onr e n e e n e e n l s e n lee n l s e n e e e n e e onn n &n le s nn r onr onn n e nn onn n e onn n e A i nonr onn e n e o on n wn onn nn l r nn nn nn onr s n e e nn c e oa e oo s eoo s e oo s e oo s n D t os n s e oo k s c e oo a r e e o r r ne o r r er n r P s s nr n P s s tcer o r r ne o r r gr n P s s r P s s P s s P s s r P s s n a n o r r e o r r n i e o r e s s e e eP s s ee eP s s ee iP s s ee P s s ee P s s ee N u tap s s e cPP r cPP l A F r r cPP t P r cPP p r cPP t r cPP s r cPP r n s eei eei e e s s s cP yg e cP yg cP yg cP i yg to ee e ieei s e ei neei s s s s a T b pcP i g a cP yg IncP yg i y y r n r n n yr n n y yr n c n yr n a y gh oi y n gh oi o gh oi ga gh oi a r n n r n Mn gh oi a o S On gh oi a gh oi Ma r e L ninP s r a s r nP s r r nP s nP i e et ht ei n ie T e e ni i e c ni ie ni ie P ni ier n ni J a r nP s r e nP s r ninP i e inet h vr e ivt s t t ei r nr t vr n i tet h v e e t h v e li et h v e l vr n At a r n d oe ta t e a a r n et a t r n et a et ah h v t a n apgTnr l pe a e i e a c n er n tnr lapg eie l pg e i e lt ei t nr lapy f i pel SE TMOll S I' G ei unr t t r l ei cnr l kr e a pe a apg si e e aie a pp uie u n pape l u n e a u n Oape u n r InMOl l u n a a pc u n oa pc s a pel SE SMOl SE WMOl SF RMOl o l l u n w RMOl SE RMOl SE N Ng CC~ _ ;?4

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. UNIT DATE COMPLETED BY TELEPilONE MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) ( MWe-Net ) 1 17 2 18 3 19 4 20 O 6 22 7 23 8 24 9 25 10 26 11 27 12 28 i3 29 14 30 15 31 16 INSTRUCTIONS On this form, list the average daily unit power 'evel in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. These figures will be used to plot a graph for each reporting month. Note that when mammum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power lesel exceeds the 1003 line (or the restricted power lesel hne). In such cases. the average daily unit power output sheet should be footnoted to explain the apparent anomaly. 1 5 062

APPENDIX C OPERATING DATA REPORT DOCKET NO. UNIT DATE COMPLETED BY l TELEPHONE OPER ATING STATUS

1. REPORTING PERIOD.

GROSS HOURS IN REPORTING PERIOD: 2 CURRENTLY AUTHORIZED POWER LEVEL (MWt): M AX. DEPEND. CAPACITY (MWe Net): DESIGN ELECTRIC AL R ATING (MWe-Net):

3. POWER LEVE L TO WHICH R ESTRICTED (IF ANY) (MWe-Net):

4. RE ASONS FOR RESTRICTION (IF ANY):

TrilS MONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS RE ACTOR WAS CRITIC AL

6. REACTOR RESERVE SHUTDOWN HOURS

7. HOURS GENER ATOR ON LINE

8. UNIT RESERVE SHUTDOWN HOURS

9. GROSS THERMAL ENERGY GENER ATED (MWH)

10. GROSS ELECTRICAL ENERGY GENER ATED (MWH).

11. NET ELECTRICAL ENERGY GENER ATED (MWH)

12. REACTOR SERVICE FACTOR

13. REACTOR AVAILABILITY F ACTOR

14. UN!T SERVICE FACTOR UNIT AVAILABILITY F ACTOR UNIT Cx.PACITY FACTOR (Using MDC)

.o.

17. UNIT CAPACITY FACTOR (Using Design MWe) 18 UNIT FORCED OUTAGE RATE 19 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DUR ATION OF EACH):

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIM ATED DATE OF STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO COMM2RCI AL OPERATION):

FORECAST ACHIEVED INITI AL CRITICALITY 9 125 003 INITI AL ELECTRICITY r COMMERCI AL OPER ATION 1.16-9

INSTRUCTIONS FOR COMPLETING OPER ATING DATA REPORT Tlus report should be furnished each month by as speciGe as posuble withm space hmitations Plants m heensees. The name and telephone number of the startup and pow er ascension test phase shouf d be preparer should be prouded in the designated spaces identified here. . The mstructions below are presided to assist licensees in l reporting the data consistently. The number of the

5. Show the total number of hours the reactor was

.nstruction corresponds to the item number of the critical during the gross hours of the reportmg ;'enod.

' report f orm.

e. Reactor Resen e Shutdow n llours. The total

1. Reporting Period. Designate the month for which number of hours dunng the gross hours of reportmg the data are presented. The Gross llours are normaHy from 0001 ef the Grst day through 2400 of the last day pen d that the reactor was remmed from sente for administrative or other reasons but was available for

of the calendar month, with appropriate adjustments for

any month in which a change from standard to pe ration.

j daybght-saung time (or sice sersa) is made. The only two shorter reportmg periods are (1) the one in which

7. Hours Generator On Lme. Also called Senice llours. The total number of hours during the gross hours the imtul electncal generation occurs and (2) the one in

w!uch the reactor is shut down for decommissioning. In of the reporting period that the unit operated with breakers closed to the station bus. These hours, plus

' the fermer, the gross hours, expressed to the nearest

tenth of an hour, are those from the time of initial those hsted in Appendix D for the generator outage power generation to 2400 of the last day of the calendar hours, should equal the gross hours in the reporting month. In the f atter case, the gross hours, expressed to period.

l the nearest tenth of an hour, are those from 0001 of the

8. Unit Resene Sbutdown flours. The tote number i calendar month to the specine time of final shutdown.

of hours during the gross hours of the reporting penod i

2. The Authorized Power Lesel is the maximum that the umt was removed from senice for econ.aic or

! thermal power, expressed in megawatts, currently simdar reasons but was avadable for operation. j authonzed by the Nuclear Regulatory Commission.

9. Gross Thermal Energy Generated. The thennal t

The net Maximum Dependable Capacity is the gross output of the nuclear steam supply system during the electrical output as measured at the output terminals of gross hours of the reportmg period, expressed in j the turbine-generator dunng the rr.ast restrictive seasonal megawatt hours. i conditions less the normal station senice loads.

10. Gross Electrical Energy Generated. The electrical The net Design Electrical Rating is the nominal net output of the unit measured at the output terminals of

electrical output of the unit specified by the utility and the turbinemenerator durmg the gross hours of the

, used for the purpose of plant design. reporting period, expressed in megawatt hours. 1 Note that this item is apphcable only if restric- , ions on the power !cvel are in effect. Short-term (less

11. Net Electrical Energy Generated. The gross elec-

,t trical output of the unit measured at the output l than one month) limitations on power level need not be terminals of the turbine-generator nunus the normal

presented in this item, smce one of the important station service loads during the gross hours of the j purposes of the item is to determine if, and at what

! power lesel, a restricted power level line should be reporting period, expressed in megawatt hours. Negatne quantities should not be used. If 11 ere is no net postuve ' drawn on the chart of aserage dady reactor power. value for the period, enter zero. Smce this information is used to develop figures on capacity lost due to restrictions and because most users 12-18. For umts stdl in the startup and power of the " Operating Plant Status Report" are primarily ascension test phase, items 1218 should not be com- . interested in energy actually fed to the distnbution puted. Instead, enter N A in the current month column. ) system. it is requested that this figure be expressed in These seven factors should be computed startmg at the MWe-Ne t in spite of the fact that the Ogure must be time the unit is declared to be in commercial operation. ) denved from MWt or percent power. The cumulative figures in the second and third columns j should be based on commercial operation as a starting

4. Reasons for Restriction (if Any). If item 3 is date. Iloweser, units already in commercial o;>eration.

used, item 4 explains why. Brief narratise is acceptable. for which cumulatise figures base been based on Cite references as appropriate. Ir dicate whether restric-different starting dates. need not r,ecpleulate the cumula-9 i tions are self-imposed or are regulatory requirements. Be } }} Q yl{ tise figures. l.16-11

12. Reactor Senice Factor. Compute by diuding

18. Unit Forced Outage Rate. Compute by dividing hours reactor was critical (item 5) by the gross hours m the total forced outage hours (from the table in the reporting period (item 1). Express as percent to the Appendix D) by the sum of hours generator on line nearest tenth of a percent. During months when the unit (item 7) plus total forced outage hours (from the table is shut down for the entire period because of nonreactor in Appendix D). Express as percent to the nearest tenth problems, enter "Not Applicable" and explain in the of a percent.

Summary of Appendix D. Do not include resen e shutdown hours in the calculation.

19. Shutdowns Scheduled to 13egin in Next 6 Months. Include type (refueimg. maintenance, other),

13. Reactor Availability Factor. Compute by divid.

proposed date cf start of shutdown, and proposed length of shutdown. It is recognized that shutdowns may be ing the reactor available hours (items 5 plus 6) by the scheduled between reports and that this item may not be gross hours in the reporting period (item 1). Express as all inclusise. lie as accurate as possible as of the date the percent to the nearest tenth of a percent. report is prepare 1.

14. Unit Senice Factor. Compute by dividing hours

20. Self-explanatory.

the generator was on line (item 7) by the gross hours in the reporting period (item 1). Express as percent to the

21. Self-explanatory. Note, however, that this infor-nearest tenth of a percent. Do not include reserve ati n is requested for all umts in startup and power shutdown hours in the calculation.

ascension test status and is not required for units already 5" # * ** '#i *t P#' *i "'

15. Unit Availability Factor. Compute by dividing the unit available hours (item 7 plus item 8) by the grosa Test Status is defined as that period follawmg initial hours in the reporting period (item 1). Express as criticality during which the unit is tested at successively percent to the nearest tenth of a percent.

higher outputs, culminating with operation at full power for a sustained period and completion of warranty runs.

16. Unit Capacity Factor (Using MDC). Compute by Followmg this phase, the unit is generally considered by dividmg net electrical energy generated (item 11) by the the utdity to be available for commercial operation.

product of maximum dependable capacity (i'em 2) times the gross hours in the reporting period (item 1). Date of Commercial Operation is dermed as the date Express as percent to the nearest tenth of a percent. that the unit was declared by the utihty owner to be available for the regular production of electricity,

17. Unit Capacity Factor (Using Design Electrical usually related to the satisfactory completion of qualifi-Rating). Compute as in item 16, substituting design cation tests as specified in the purchase contract and to electrical rating for maximum dependable capacity.

the accountine policies and practices of the utthty. O 1.16 12

ST N E M ) M ) N O N I C I A A L N O E Y E / L P l S P ODN X N M T B N N X IT NO E( A A D O O E( IRGA l I CAI T T R N D T E E i E P O K T T C R TNN M E A U SI I R E NMER) .A) L E I C L N N N L E IAS T R IA AVL I MR O E U P VI FE YR XIT LA A C IA T S L D M T T G OR ER N C CP T RT E A AL R PX I X O C NR N S S TO E T E E TO C E O.ILAT NS IT( LLA( R M TEL A C INAR AAMR EI R P NI NUU RI RE DUU Ol O O UI l' GE LM l ONN Tl Ei i C SQAI LP DPT li AAUT ALMRRO AOO TMMAO RA1 : : .. 1 E. : : : E : 0 CDE 1 G1 M1 23 4 2 SN ) ) O 1( 2 I ( TC ) 2 U R( N D W OR E E F OR W R ODO T O R DG C P E ON AG D W HI EN T T I O TRI X E C P M UEU D l HH D D i N T S T E E N N R P A O P S M A N ) W T 1 R ( O O N D P O T E SA U R E H R S T IN N) OS U I R TA U R O H U( D D E D L E U EC PR D E Y O T H F C . S F S E TA D Y R A M O M N U S sNW g'@ .~

UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS required to be initiated t,y no later than the v eckend follcwing discovery of ma off-normal wndition. It is Thas report should describe ah plant shutdowns dur-recognized that some judgment is required in categori-ing the report period. In addition, it should be the zing shutdowns ir this way. In general, a forced shut-source of explanation of significant dips in average down is one that ould not have been completed in the power lesels (Appendtx B). Each significant reduction in absence of the condition for which corrective action was power level (greater than 207c reduction in average daily taken. power level for the preceding 24 hours) should be noted, esen though the ' unit may not have been shut down Duration. Self explanatory. When a shutdown extends completely. For such reductions in power level, the beyond the end of a report period, count only the time duration should be listed as zero, the method of reduc-to the end of the report period and pick up the ensuing tion should be listed as 4 (Other), and the Comments down time in the following report periods. Report dura-c.lumn should explain. The Comments column should tion of outages rounded to the nearest tenth of an hour be used to proside any needed explanation not ade-to facilitate summation. The sum of the total outage quately desenbed by the coded columns. Please do not hours plus the hours the generator was on line (item 7 of add to the list of codes or legends now fumished. Simi. Appendix C) should equal the gross hours in the report-larly, do not add additional columns. ing period (item 1 of Appendix C). Reason. Categorize by letter designation in accordance Number. Tms column should indicate the sequential with the table appearing on the report form. If category number assigned to each shutdown or significant reduc-H must be used, supply brief comments, tion in power for that calendar year. When a shutdown or significant power reduction begins in one report Method of Shutting Down the Reactor or Reducing period and ends in another,an entry should be made for Power. Categorize by number designation in accordance both report periods to be sure all shutdowns or signifi-with the table appearing on the report form. If category cant power reductions are reported. Until a unit has 4 must be used, supply brief comments. achieved its first power generation, no number should be assigned to each entry. Corrective Actions / Comments. Use this column to am-plify or explain the reasons for each shutdown or signifi. Date. This column should indicate the date of the start cant power reduction, with the corrective action taken, of each shutdown or significant power reduction. Report if appropriate. The Comments column entries should as year, month, and day. August 14,1975 would be provide identification of each shutdown or significant reported as 750814. When a shutdown or significant power reduction that occurs as a direct result of a re-power reduction begms in one report period and ends in portable occurrence on which a report has been or will another, an entry should be made for both report be submitted. (This information may not be immediately periods to be sure all shutdowns or significant power evident for all such shutdowns, of course, ;ince further reductions are reported. investigation may be required to ascertan whether or not a reportable occurrence was involved.)% hen a direct Type. Use "F" or "S" to indicate either " Forced" or correlation can be made betwe. 4 a given shutdown and a " Scheduled," respectively, for each shutdown or signifi-5pecific reportable occ"rrencc report, the Comments cant power reduction. Forced shutdowns include those column entry should state the reportable occurrence report number and date. ' Ete that thn differs frorn the Edison Electric Institute (EEI) Summary. Write a brief sumn.ary description (3 to 4 deGnitions of "i orced Partial Outage" and " Scheduled Partial sentences) of the highlights of operation of the unit for Outare " l'or these terms. I El uses'a change of 30 MW as the break point. For larger power reactors 30 MW is too srnall a the reporting month. Includi any comments required by t hange to warrant exrtanation. item 12 of Appendix C. 9 k b 1.16-14

APPENDIX E LICENSEE EVENT REPORT CONTHOL BLOCK l ! l l l l j LICENSE EVENT LICE NS E E NAME LICENSE NUMBER TYPE TYPE oi l l I l I I _] I I i-l i I I I l1 I l Il I I l I l 9 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT D ATE F.E PO RT D AT E h 0N'Tj l l {_j ] l l l l ~l l l l l {l } l l l l l l l l l l l 7 8 57 58 59 60 61 68 69 74 75 80 E VENT DESCRIPTION I o I go 7 89 f I 80 7 89 i El 80 7 89 j O l 80 7 89 I 80 'SYSTE M C AUSE COMPO NT COMPONENT CODE CODE COMPONENT CODE S UPP LI E R MANUFACTURER VIOL ATION MI I I U l l I l l U j l l l l y 7 89 10 11 12 17 43 44 47 da C AUSE DESCRIPTION l O l 1 80 7 89 1 1 1 80 7 89 F ACILIT Y METHOD OF STATUS % POWE R OTH E R ST ATUS DISCOV E R Y DISCOVE RY DESCRIPTION EE LJ l I I I L 1 L_J l 1 7 8 9 10 12 13 44 45 46 60 A T VI CONTENT LOCATION OF RE LE ASE RE LE ASE D OF R E LE ASE AMOUNT OF ACTIVITY 8 L_J L_J l i I I 80 7 8 9 10 11 44 45 PE RSONNE L E XPOSU RES NUMBER TYPE DE SC RIPTIO N I 31 l 1 1 LJ 80 7 89 11 12 13 PE RSONNE L INJU RIES NUMBER DESCRIPTION 1 1 1 I I I I 80 7 8 9 11 12 ^ PROB ABLE CONSEQUE NCES I i l 80 7 89 LOSS OR D A*A AGE TO F ACILITY TYPE DESCRIPTION l L_J 80 7 89 10 P'J B Li CI T Y I 80 7 89 A DDITION AL F ACTORS l 1 I 80 7 8 3 1 81 80 7 89 PHONE. NAME 25 068 !.lb-is

UNITED STATES F ] NUCLEAM REGULATORY COMMISSION WASWNGTON, D. C. 20555 pg37,,g,gg,gg3 ,,,g g vN TED ST ATE S hvC 4 E A8 orncia' Su"",'" , ooo L asummummeJ atcutATony couwission sc PENALTYE O 8 O 125 069}}