ML20058K585

Requests Proposed Revs to Administrative Controls Section of TS to Meet Quidance Contained in Encls Re Plant Reporting Requirements

ML20058K585
Person / Time
Site:	Monticello
Issue date:	09/28/1972
From:	Skovholt D US ATOMIC ENERGY COMMISSION (AEC)
To:	Dienhart A NORTHERN STATES POWER CO.
References
NUDOCS 9102120525
Download: ML20058K585 (20)

Text

{{#Wiki_filter:- -w, [, =, N l C) W' tog UNITED STATES j l-g ) [MM, ATOMIC ENERGY COMMISSION . J' Q,.* ( I WAsmNGTON, D.C. 205 0 i %.csi a i '*"5 * / September 28, 1972 l Docket No. 50-263 j i 1 l Northern States Power Company ATTN: Mr. A. V. Dienhart l Vice President - Engineering 414 Nicollet Avenue l l Minneapolis, Minnesota 55401 i 4 Gentlemen: r i As the number of nuclear plants in operation becomes progressively I larger, the data from these plants become increasingly important. l Th eref ore, it is highly desirabic tuat data reporting be consistent i l from plant to plant. This consistency will facilitate the analysis, l cvaluation and comparison of data on the Safety and Environmental l Ef fects of tne operating plants. l, The Administrative Controls Section of Tecnnical Specifications f delineates reporting requirements. In the near future, we propose l to revise this Section of Technical Specifications to assure reporting consistency and to conf orm as nearly as possible to Safety Guides 16 and 21. We are enclosing copics of these Guides for your information. i Also enclosed are suggested Technical Specifications that cover the j I ' i Plant Reporting Requirements. l Pleasc submit within sixty days, proposed revisions to the Administrative j 4 j Controls Section of your Technical Specifications which meet the , j guidance set fortn in the enclosures to the extent practical for your facility. The proposed revision should be submitted in three signed and thirty-seven additional copies. Although all of the provisions of Safety Guides 16 and 21 may not be l included in the present Technical Specifications for your f acility, ..e I request that you immediately address the reporting format of the Guides, and, ta the degree practical for your facility, make measure-l ments and analyscs equivalent to those specified in tne Guides. 'l j Waere you coll (ct alternate, different, or additional data that j 1 should be reported separately,, lease report these data in units I' and style as similar as feasible to those of the Guides. 4 i, I t i l t i i,i 9102120525 72CF728.... CF AIX3CK 05000263 CF._ { =

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For those subjects addressed in the Safety Guides which you do not propose to adopt in your reports, we request that you submit the i following additional information: 1. A description of those areas where it is not practical I in your facility for you to follow measurements I prescribed and the reporting format of the Guides, i 2. A description of those measurements which depart ] either in frequency or in type of analysis from the acceptable program described in the Safety l Guides and a justification for the adequacy of i your alternate program. l Thank you for your cooperation in this ef fort to provide a consistent means of reporting information on operating data and effluent releases from nuclear power facilities. i I j Sincerely, i

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s 64?/w f f. - ,,,.,9j,g l Donald J 'Skovholt l Assistant Director for l Operating Reactors j Directorate of Licensing Enclosures. l 1. Safety Guide No. 16 '{# U (,f "d 'C l bf 00fh} l 2. Safety Guide No. 21 l 3. Plant Reporting Requirements l cc: Donald E. Nelson, Esquire f l VP and GC l Northern States Power Company l j 414 Nicollet Avenue Minneapolis, Minnesota 55401 I 1 i l l I I e i e i 'i t 3

1[ o o P PLANT REPORTING REQUIREMENTS 6.12 The following information shall be submitted in addition to 6.12.1 the reports listed in Tabic 6.12-1 and required by Title 10, code of Federal Regulations. 6.12.2 Routine Reports: Operating Reports a. Operations Reports shall be submitted in writing to the j Deputy Director for Reactor Projects, Directorate of Licensing, USAEC, Washington, D. C. 20545. (1) Startup Report A summary report of unit startup and power escala-tion testing shall be submitted following receipt of operating licenses, following amendments to the licenses involving a planned increase in power level, has a following the installation of fuel that different design and/or has been manufactured by a different fuel supplier, or following modifications to an extent that the nuclear, thermal, or hydraulic performance of the unit may be significantly altered. shall include a description of the measured The report values of the operating conditions or characteristics obtained during the test program and a comparison with design predictions and specifications. Any corrective actions tnat were required to obtain satisfactory oper-ation should be described. Startup reports shall be submitted within 60 days f ollowing commencement of commercial power operation, i.e., initially following synchronization of the turbo-generator to produce commercial power or resumption of commercial power operation 6.12-1

9 9+ i I V. i i (2) First Year Operation Rcport i l A report shcIl be subndtted within 60 days af ter t I completion of the first year of commercial power i operation as defined above. This report may be incorporated into the semiannuni operating report and shall cover the following: l t l (a) an evaluation of unit performance to date in comparison uith design predictions and ~ specifications; (b) a reassessn nt of the safety analysis submitted with the license application in light of I measured operating characteristics when such '( I measurenents indicate that there may be sub-stantial variance from prior analyses; ~ l (c) an assessnent of the performance of structures, i systems and components important to safety; l l 4s l (d) a progress and status report on any iters identified as requiring cdditional information during the operating license review or during f the startup of the plant, including itern dis-cussed in the AEC's safety evaluation, itens on [ l which additional informati.. was required as l l i i 6.12-2 ) t 6

O O I p conditions of the license and items identified in the licensec's startup report. (3) Serdannuni Operating Reports l f l Routine operating reports shall be submitted within l 60 days af ter January 1 and July 1 of cach year, f i, The first such period should begin with the date of initial criticality. These reports should include the follewing: ~ ,( i (a) Operations Su:=ary l A sunnary of operating experience occurring during the reporting period that relate:; t o the l safe operation of the plant, including a f sum: nary of: t i (i) changes in plant design, l (ii) performanca characteristics (e. g., equiprent and fuel performance), 9 (iii) changes in procedures which were riecessitiated by (i) and (ii) or uhich i l I othemise were required to improve the safety of facility operations, l 6.12-3 t b ~. ~. ~. _ _... - - ~,..,. ,.. -,x ee. se .._-w.

L g-( [, I h: 9 t !, ] (iv) results of surveillance " tests and l inspections required by these technical specifications, f t i k --4 (v) the results of any periodic containment !. r leak rate tests performed during the t s rerorting period, h (vi) a brief summary of those chang,es, tests [ and experiments requiring authorization 5 E from the Commission pursuant to 10 CFR j 50.59(a), and !i 3 (vii) any chan,a,cs in the plant operating l 4 orgnuization which involve positions which are designated as key supervisory i ] personnel on Figurc 6.2-1. t 4 J s t (b) Power Generation j A summary of power generated during the j e i reporting period including: m d 1 (i) gross thermal pcuer generated (in hvd) j 1 4 1 4 (ii) gross electrical power generated (in 4 wo a 9 h 6.12-4 s. Cf*pP%&@ l??$$%l:gtthjpng??:D , ~'L^".1.., # ?!??%& n$ k )

l-9 9~ l l (iii) net electrical power generated (in !Wd) b-

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l l (iv) number of hours the reactor was critical l (v) number of hours the generator was on-line 1 i r (vi) histogram,f thermal pouer vs. tire i l l (c) Shu t d owns l l Descriptive material covering all cutages f occurring during the reporting period. For L i l cach outage, information shall be provided on: r l i i (i) the cause of the outat;c, i i i l (ii) the rnethod of shutting -down the reactor; ( l l

c. g., t rip aut enatic rundown, or manually controlled deliberate shutdown, l

(iii) duration of the outage, (iv) unit status during the outage; e.g., cold shutdcran or hot shutdown, (v) corrective action taken to prevent l l repetition, if appropriate. 1 i i t 6.12-5 [ \\ \\ l l l 6 t l = .-A... -,g wy p:p l re- . ~ + .g -i.,,,g me-

E. o ,s g_.- p p. ,.,.,s-i .e o 4 i V l (d) Naintenance 'l 'l i i l A diccussion of safety-related maintenance f (excluding preventative maintenance) perforned during the reporting period on systems and i; components that are designated to prevent or mitigate the consequences of postulated acci-j I dents or t o prevent the release of significant i amounts of radioactive material. Included in this category are systens and components which l l are part of the reactor coolant pressure l boundary defined in 10 CFR 550.2(v), any part of the engineered safety featurcs, or l i associated service and control systers that are required for the nornal operation of engineered { safety features, part of any reactor protection or shutdown cfstem, or part of any radioactive waste treatment handling and disposal system or other system which may contain significant amounts of radioactive material. For ny ral-i functions for which corrective maintenance was I required, information shall be provided on: (1) the system or component involved, (ii) the cause of the malfunction, (iii) the results and effect on safe operat ion, 1 l 6.12-6 l l l i E EEMEMM g. p. = = mE.=-.elmillW9lhw gj_ _ m. --.+. .a g u-~ g w m_e_.y ggg g m wy _p,, wr.y.;_.4 y _.- u ;- +g a wwp. - +.,.w g g p g*= ~ +. rw e ~ m: r, n 'tw... u,.

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I I 1 i 1 I [ (iv) corrective actica taken ' o prevent t I repe tit ion, J l (v) precautions taken to provide for reactor [ t safety during repair, i i i (e) Changes, Tests and Experirents 1 A sumary of all changes in the plant design } and procedures that relate to the safe oper-ation of t he plant shall be included Jn the i t i Operations Sunmary section of these seniannual re po rt s. Changes, tents, and experin.cnts per-l formed during the reportinn period that require l l aut hori zat i on fron the Conninsion pursuant to j l 10 Crit 50.5?(z.) are covered in paranraph l 6.12.1.a(3)(a)(vi) of these technical specifi-i c at ion s ; h cr.ic ve r, those changes, tests, and e c::perirents that do not require Connission I authorization pursuant to 550.59(a) shall bc t addressed. The report shall include a brief i description and the summary of the safety cvaluat i on f or t h os e chan ges, tests, and t expe rimen t s, carried out without prior Commis-I L sion approval, pursuaat to the requirenents of ~ 550.59(b) of the Con: mission's regulations, that "The licensee shall furnish to the Commission, + i 6.12-7 r f

t o o l l I l annually or at such shorter intervals as may be specified in the license, a report containing a brief description of such changes, tests, and experimen t s, including a summary of the safety evaluation of each". i I (f) Radioactive Effluent Releases I l A statement of the quantities of radioactive cffluents released from the plant, with data l summarized on a monthly basis following the format of Appendix A of USAEC Safety Guide 21 of January 1972: l l (1) Gaseous Effluents (a) G,r o s s R.- .ctivity Releases (1) Total gross radioactivity (in curies), including noble and activation gases released. l (2) Maximum gross radioactivity release rate during any one-hour period. f (3) Total gross radioactivity (in curies) by nuclide released, based on repre-sentative isotopic analyses performed. (4) Percent of technical specification limit. l 6.12-8

t "l O O i l (b) Iodine Releases l J i ) (1) Total iodine radioact.vity (in curies) by nuclide released, based on repre-l sentative isotopic analyses performed. l (2) Percent of technical specification j i limit for I-131 released. l t (c) Particulate Releases j I l l (1) Cross radioactivity (B, y) released l i (in curies) excluding background radioactivity. i (2) Gross alpha radioactivity released (.4n curies) excluding background i radioactivity. i (3) Total gross radioactivity (in curies) f of nuclides with half-lives greater { than eight days. l l i j (4) Percent of technical specification l I limit for particulate radioactivity r l I I with half-lives greater than eight l days. j l l l l 6.12-9 l

i O o l l l (ii) Liquid Effluents (a) Gross radioactivity (B, y) released (in curies) excluding tritium and average concentration released to the l unrestricted area. I I I (b) Total tritium and alpha radioactivity l l (in curies) released and average con-l I l centration released to the unrestricted l crea. l (c) Total dissolved gas radioactivity (in i I i curies) and average concentration released to the unrestricted area. l t (d) Total volume (in liters) of liquid waste released. (c) Total volume (in liters) of dilution water used prior to release from the { i I l restricted area. (f) The maximum concentration of gross I radioactivity (S, Y) released to tne unrestricted area (averaged over the period of release). i I I { l 6.12-10 l l

ges N J gi O O U i i' t it: i i i I l l (g) Total gross radioactivity (in curies) ) by nuclide released, based on repre-l sentative isotopic analyses performed. i t i l (h) Percent of technical specification j l limit and 10 CFR Part 20 concentration limits for unrestricted areas. j (iii) Solid Waste i i I (a) The total amount of solid waste packaged (in cubic feet). l l (b) The total estimated radioactivity l (in curies) involved. l l (c) The dates of shipment and disposition i (if shipped offsite). I (g) Environmental Monitoring (1) For each medium sampled, e.g.,

air, l

baybottom, surface water, soil, fish l including: f l 1 (a) Number of sampling locations, (b) Total number of samples, u.12-11

..ri ~ ~ _ -. L! o o l l rl i l i I l (c) Nur.ber of locations at which levels are found to be significantly above local backgrounds, l (d) Ilighest, lowest, and the annual I average concentrations or IcVels of I radiation for the sanpling point I uith the highest avera:;e and description of the location of that 3 point with respect to the site. l I (ii) If 3cycJs of radioactive materials in i i environnental cedia indicate the likeli-l hood of public intakes in excess of 1% of thcse that could result from con-tinuous exposure t o the concentration values listed in Appendix B, Tab 1c II, Pa rt 20, esticates of the likely resul-tant exposure to individuals and to l l population groups, and assunptions upon l which estimates are based shall be provided. l l l (iii) If statistically significant variaticas t of offsite environn2ntal concentrations l l with time are observed, correlation of these results with effluent releasc i 6.12-12 + k i

w_ ~ -.e m,e -- -p o o f ~ i l 1 i i ( t l shall be provided. j i i I (h) Occupational Personnel Radiation Exposure I! A tabulation of personnel exposures shall be [ reported for the year (or first six months) '( ) in the following groups: less than 100 mrem, f 100 - 500 mrem, 500 - 1250 mrem, 1250 - 2500 mrem, il t 2500 - 5000 mrem, above 5000 mrem. An explanation l for all personnel exposures greater than 500 mrem ll .t in six months or the year shall be provided. I! i s ; l 6 l' 6.12.3 Non-Routine Reports i i i t 1 i i i t t l l a. Reporting of Abnormal Event,s {'!c l l (1) Abnormal Occurrence Reports j, i Notification shall be made within 24 hours by telephone l telegraph to the Director of th.,e Regional Regulatory o I Operations Office, f ollowed by a writ ten repor t within i 10 days to the Deputy Director for Reactor Frojects, [ Directorate of Licensing (cc. to the Director of the Re2 onal Regulatory Operations Office) in the event i of the abnormal occurrences as defined in Section l.0. The written report on these abnormal occurrences, t I [ 6.12-13 l' aww-- v -w-- au a

&;xp;tz:v - - ~ I d and to the extent possible, the preliminary telephone f and telegraph notification, shall: (a) describe, analyze and evaluate safety implications, (b) outline l tne measures taken to assure that the cause of the I condition is determined, and (c) indicate the I corrective action (including any changes made to l l l the procedures and to the quality assurance program) taken to prevent repetition of the occurrence and of similar occurrences involving similar components or systems. i f t In addition, tne written report shall relate any failures or degraded performance of systems and i components for the incident to similar equipment I failures that may have previously occurred at the plant. The evaluation of the safety implications I of the incident should consider the cumulative experience obtained f rom the record of previous l failures ar.d malfunctions of the affected systems and components or of similar equipment. i i b. Reporting of Unusual Events l i i A written report shall be forwarded within 30 days to the f I Deputy Director for Reactor Projects, Directorate of Licensing, i ..nd to the Director of the Regional Regulatory Operations j t i Office, in the event of: I l I i (1) Discovery of any substantial errors in the transient [ I or accident analyses, or in the methods used for such \\ analyses, as described in the Safety Analysis Report t or in the bases for the technical specifications. 6.12-14

? o 9 1 1 (2) Any substantial variance f rom perf ormance specifi-cations contained in the technical specifications l or in the Safety Analysir Report, l 1 (3) Any condition involving a possible single failure which, for a system designed against assumed single failures, could result in a loss of the capability of the system to perform its safety function. 6.12.4 Special Reports Special reports shall be submitted in writing within 90 days to the Deputy Director for Reactor Projects, Directorate of Licensing, USAEC, Washington, D. C. 20545. Special reports shall be submitted covering inspections, tests and maintenance that are appropriate to assure safe operation of the plant. The frequency and content of these special reports are determined on an individual case basis and designated in these technical specifications. Examples of subjects for such reports include: (a) In-service inspection. (b) Tendon surveillance. (c) Containment structural tests. 6.12-15 i I i I m t i

~4 Mwunwn;fn--: ~'( l ~ O O l ~ l r (d) Special maintenance reports. (e) Authorization of changes, tests, and experiments in accordance with 10 CFR 50.59. l (f) Containment leak rate tests. l (g) Radioactive effluent releases. l (h) Materials radiation surveillance specimens reports. l l (i) Fuel performance following each refuelin6 or partial refueling. + i 4 1 4 i 4 N t i t 6.12-16

y p l v n,,, E M T/", LE 6.12-1 Rrvo"TI':r. 51*vA"sv L Technical i I Specifications IEC Noti'icatinn Written 4enort Uithin i Pa rne raoh Reculation Report 'Ji t h i r-10 Dnts 30 Dnvs 6un. 1ve. 6.6 20.403(n) Severe Accidert Ina olvine Ireediatelv DRO i Licenocc' "n t e rip i l L 6.6 20.402 Loss or Licensed v terial Innediately DRO a 9 6.6 73.42 Special Nuclear "cterial 1 r,edia t niv' Unnecounted for g 3 6.6 40.64(c) Th ef t or n.la..r l 71 version Irredintelv u l of Sourca "aterial 6.6 70.52 Accidental Critical!tr or Pro-ntly Loss or S nect :-) 'cucient Mat'c r ia l 6.6 70.54 Trans fer or Snecial P ronn t a-Nucicar aterin! i i Reccint of Snecial ';uclear 3 Material IEC I 6.6 40.64 ( a) r Trans er or Scurce '*nterial Prenntiv h Receipt of Source "cterial /EC F 6.6 20.403(b) Accidents Involvin:' DRO Licensed "aterici 24 hours 6.6.2.a 50.36 AbrormaJ Occurre co 2'4 hours DL/DRO L 6.6 20.405(n) Ove rex,osure er Excess ive DRO l Radiatton T.evel l l 6.6.2.b 50.36 linusual Events DL/DRO m v m t e e+ - *_ _ _ _, -_ _ -

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T t. .r' ; ./ T/.ILE /4.12-1 (Con tinued) i. DFT'02TI'm SimA"Y r Technical 1 Spe c i ficat ions AEC Notification Written #enort THthin Paracranh "eculation Renort Ui th !.i lo navs in Pays 6 Fo. 1Y 6.6 20.403 Personnel E:q asure ~ DR (Terrinat ed E nloyecr,) S ecini Nucicar "aterini AEC' 6.6 70.53 P ( Status h 6 6.6.1.a(1) 50.36 Startun Fenort DL 1 6. 6.1. a ( 3) 50.36 Seninnnual operntinn DL 6.6.1.a(2) 50.36 First Year Orcration DL i i 6.6 20.407 Personnel E :nes ure PR i and "cni t ori nc 6.6.3.e 50.59(d) Changes, Tes t, and DL i Experiments 8 6.6.3.f Proposed Apncadix Contain'ent Lenk DL Part 50 Rate 1 UR - Director of Regulation, DL - Directorate of Licensing, DRO - Directorate of Regulatory Operations E.h, at 2 See 10C7R73.42 for details on renortinr, tires. -4 3 See 10CFn40.64(c) for details en recorti n-tires. ' 1 4 U.S. At onic Enerc,y conri ssion, P.O. tiex t, c', t : Ridee, Ten ensee 3783'1 .h a ter termination, whichever is earlier. -{ ' ( 5 within 30 days ef ter deternininn excesure or 90 days r 'I tes t in ' or cor ence-ent o' co-crcial ceer oneration, 6 Within 60 days felloring com,letien or whichever co cs ri ry t, 7 Ar.C auth ori rnt i en is recui red nrier to rer er-i c, th e charme, tes t, or ex 'er i-c t i n this r cat e : cry. S Perort en firs t t e:t due 3 nenths after cor, M ien er test; notirication or etber tests de, n'< cn

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