ML20237G758

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Applicant Exhibit A-1A,consisting of Vol V (B) to TMI-2 Reactor Coolant Inventory Balance Testing, Dtd 850905.Vol Discusses Tabs 10-14
ML20237G758
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 09/08/1986
From: Stier E
GENERAL PUBLIC UTILITIES CORP., STIER, E.H.
To:
References
LRP-A-001A, LRP-A-1A, NUDOCS 8708140186
Download: ML20237G758 (291)


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TMI-2 REACTOR COOLANT INVENTORY BALANCE TESTING N!! CLEAR REGULATORY COMMl20N Dock.t Ra d48 /

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TMI-2 REACT 0R C00LANT INVENT 0RY BALANCE TESTING PREPARED FOR GPU NUCLEAR CORP. 1 l

BY EDWIN H. STIER I

I l

INVESTIGATIVE STAFF- i l

FREDERICK P. DE VESA ROBERT T. WINTER l

SEPTEMBER 5, 1985 VOLUME V (B)

DOCUMENT

)

Tabs 10 - 14 1

f i

l INDEX TO DOCUMENTS 1

l Tabs 1 Letter, P. R. Clark to E. H. Stier, February 1, 1984.

2 Statement of Facts submitted by the United States, (United l States of America v. Metropolitan Edison Company),  !

February 1984.

1 3 Statement of Metropolitan Edison Company With Respect to Plea Agreement, (United States of America v. Metropolitan Edison Company), February 1984.

4 TMI Unit 1 and 2 Operations Department Shift Assignment, January 6, 1978; August 15, 1978; January 1, 1979.

(Includes TMI 1 and 2 Shift Schedules, August 15, 1978 and January 1, 1979).

5 Metropolitan Edison Company, Three Mile Island Organization Charts, (various dates - 1978 and 1979). I 6 Metropolitan Edison Company, Position Descriptions for:

Vice President - Generation, Met Ed Unit Superintendent, Nuclear Unit Superintendent, Technical Support Supervisor of Operations TMI Nuclear Shift Supervisor Shift Foreman Control Room Operator 7 TMI-2 Corrective Maintenance Work Requests and Job Tickets (in record number order) .

8 TMI Station Radiation Work Permit Detail List (excerpts),

October 1978-January 1979.

__ -____ - _ _~

9 TMI-2 Radiation Work Permits (in record number order) .

10 TMI-2 Daily Plant Status Reports (" Morning Report") and Shift Supervisor Turnover Notes for: -

October 16-19, 1978 November 8, 1978 December 20, 26-31, 1978 January 1-15,'1979 February 12, 14-15, 18-19, 1979 March 1-27, 1979 i

11 10 Code of Federal Regulations 50 (excerpts) l l

@@ 50. 36, 50.36(c)

Appendix A i 12 U.S. NRC Regulatory Guide 1.45 Reactor Coolant Pressure Boundary Leakage Detection Systems, May 1973.

13 U.S. NRC Regulatory Guide 1.16 Reporting of Operating Information, Appendices A-E, Rev. 4, August 1975.

14 TMI-2 Technical Specifications (excerpts) 1.14-1.17, 3.4.6.1, 3.4.6.2, 4.4.6.2 6.5.1.6, 6.9.1.8, 6.10.1d, Table 1.1 15 TMI-2 Final Safety Analysis Report, Supplement 3.

16 Standard for Light Water Reactor Coolant Pressure Boundary Leak Detection, Instrument Society of America, ISA-S 67.03, 1982.

17 TMI Administrative Procedure 1010, Technical Specification Surveillance Program, Rev. 13, January 9, 1979.

18 TMI Administrative Procedure 1012, Shift Relief and Log Entries, Rev. 8, November 4, 1977.

l 19 TMI-2 Surveillance Procedure 2301-3Dl, RCS Inventory, Rev.

I 2, May 4, 1978.

, I i i

! i 20 TMI-2 Operating Procedure 2103-1.2, Soluble Poison Concentration, Rev. 4, June 12, 1978.

l l

l t l l 21 TMI-2 Temporary Change Notice (TCN), No. 2-79-070, March  !

! 16, 1979.

l 22 Plan of the Day (POD) Meeting Minutes (with Work Item j Lists and Supplemental Work Lists) :

l October 23, 1978 January 5, 1979 January 8, 1979 January 9-14, 1979  ;

l March 15, 1979 '

March 23, 1979 23 Shift Supervisor's Meeting Minutes:

l October 5, 1977 I July 11, 1978 1 24 Shift Foreman's Meeting Minutes:

l October 18, 1978 January 4, 1979 March 22, 1979

Ei

-4 -

25 General Office Review Board (GORB) Meeting Minutes, January 10, 1979.

1 26 Plant Operations Review Committee (PORC) Minutes, March j 5-9, 1979.

i 27 Generation Review Committee (GRC) Meeting Minutes, November 30, 1978.  ;

l 28 TMI-2 Licensee Event Report 78-62/IT (Draf t) , November ,

1978. l 1

29 TMI-2 Licensee Event Report 78-62/lT, November 1, 1978, f (with) cover letter, J. G. Herbein to B. H. Grier (NRC},

November 1, 1978).

30 Document Review Sheet for LER 78-62/lT-(with PORC Action  !

Item tracking and closeout documentation - circulates first draft LER).

31 Letter, J. L. Seelinger to B. H. Grier (NRC), (Prompt  !

Report of Reportable Occurt6nce. -Includes internal memorandum, Seelinger to Herbein, Troffer and Lawyer) ,

October 19, 1978.

32 Metropolitan Edison Company correspondence Accountability Check Sheet, (concerning LER 78-62) , November 1, 1978.

t 33 US NRC (D. Haverkamp) Inspection-Reports:

November 8, 1978 January 5, 1979 January 26, 1979

l 34 Floyd, J. R., Operations Memo 2-78-19, October 20, 1978.

35 Floyd, J. R., Operations Memo 2-78-2, December 23, 1977.

36 Letter, J. Seelinger to N. Palladino (NRC), August 9, 1984.

37 Letter, J. R. Floyd to N. Palladino (NRC), August 13, 1984.

38 Letter, G. A. Kunder to N. Palladino (NRC), August 13, 1984.

39 Metropolitan Edison Company, G. A. Loignon - Lead Auditor, ,

I QA Audit Report 78-31 (includes checklists, findings and working notes) , January 24, 1979.

40 TMI-2 Surveillance Procedure 2301-S1, Shift and Daily Checks, signed-off data sheets for Reactor Building Sump l surveillance, December 18-20, 1978; January 1-15, 1979. l l

41 TMI-2 Primary Radwaste Auxiliary Operator's Log

, (excerpt s) , October 16-24, 1978, January 7, 1979, l March 23, 1979.

42 TMI-2 Utility Printout (excerpts showing Reactor Building Sump level indication for one-minute intervals) ,

January 9, 1979.

43 TMI-2-Control Room' Alarm Printout (excerpt),

January 16, 1979, (establishes duration of RB sump level -

computer point 185 on Analog Trend Recorder) .

f

- - _ _ - - - _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - ___-___-__w

I 44 Analog Trend Recorder No. 4 Strip Chart (excerpt) , January 8-16, 1979 (annotations indicate data and RB Sump level computer point as data source).

I 45 Kunder, G. A., Informal Notes from file " Ops Notes,"

January 13, 1979.

l 46 TMI-2 Reactor Building Emergency Entrance Log, (form from l Health Physics Procedure 1630.2), October 19, 1978. 1 1 l 47 TMI-2 Control Room Daily Attendance Sheets:

l l January 16, 19'19 l October 10, 1978 October 12-14, 1978 October 16-18, 1978 December 26, 1978 - January 15, 1979 ,

March 21-25, 1979 l 48 TMI-2 Control Room Log (excerpts):

October 15-16, 1978 November 5, 1978 December 18-19, 1978 January 11, 1979 February 2, 1979 February 7, 1979 March 21, 1979 49 TMI-2 Shift Foreman Log (excerpts) :

October 5-8, 1978 October 15, 1978 October 30, 1978 December 18-19, 1978 January 11-13, 1979 February 2, 1979 February 7, 1979 February 19, 1979

l l

l 1

-50 TMI-2 Shift Test Engineer's Log (excerpt) October 16-20, 1978.

51 TMI-2 Computer Log (excerpts):

l April 8 1.2, 1978 May 23, 1978 t

May 25, 1978 October 18, 1978 November 18, 1978 November 21, 1978 i December 14, 1978 l

i 1 l 52 Notes taken by Attorney at NRC Interview of M. Coleman, l April 10, 1980.

I l

I 53 TMI-2 Field Questionnaire No. 2669, Makeup Tank and Level Transmitters, November 10, 1978.

l i

l 54 On-the-Job Training Quarterly Review: M. J. Ross, (1977-1978, 1978-1979, 1979-1980). '

i 55 Floyd, J. R., Operations Memo 2-79-01, January 25, 1979.

l

[ corrected 1/17/86]

1 I

l 1

TMI-2 Shift Test Engineer's Log (excerpt) October 16-20, 1978.

51 TMI-2 Computer Log (excerpts) :

April 8-12, 1978 May 23, 1978 ay 25, 1978 tober 18, 1978 No ember 18, 1978 i Nov ber 21, 1978 l Dece er 14, 1978 52 Notes taken b Attorney at NRC Interview of M. Coleman, ,

April 10, 1980. l 53 TMI-2 Field Questio aire No. 2669, Makeup Tank and Level Transmitters, Novembe 10, 1978.

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** < j .1 j:, - @ - v p,A 'p c4 x La E p_ x A J n tj M/ n == =4 i o ? ? : 1 A,f[dl~ns K c> xA - d eye ~sm \ o xE 4 su A n D y a nWp f 1 Aerp Ec 1& a iu qs A x = '9 94 a e __ l .J l o BB4BliiRWI Pdt100'ticlBG if Of00. DATE: 3-L ') T' 'r u'ilt t tr:fr li 'j - nc. m swlU ' trPo A5 OrJ4-7) . ArG. CORT satruel,7ntrPo A5 or_3-L-7p 9 care case :s P ~4 L15TED CAPA8!L!s._ O me NET P.M LISTED CAPABILITY 88 5 _me acT . A, = Ot. Psi n G m $ utT o =Qumn11o 68055atT 9 Ar- N nl w r Sr5TtM: itw. 7 o ar etc55unt O PRl* c Sr5 TEM: Tre.Et L*r Pat 55utt,.Igfj_ j' sdO 95 scTA/rmif9(;fi/mi s0am1e4 L sus stiA/ gam 358 ' rCt/si 8 i TRITILP'/.2/d 6Ci/el DRTIIElI"Jy TRITIUM 14 L C1/mi MTE 2-5*P7 h 3131f.4p.aC1/mi e oATri -1.7. hr 1131 4Mk .C1/mi mit 5. s .M .sg PRIMARY CHEM. OUT OF SPIC. ConolTIOR: PRIMART CHEM. OUT OF SPEC. CDeclTION: sk A)er7t9 , e., , 5  :' Pal w Y LIAK K k)h GPM PRIMARY LEAK RATE .7 N GPM I SEC. OtLM. IR SPEC./00T Or SPIC) Sit. CHEM. IC @ -)/00TOFSPEC) LIST OUT OF ' !TIONS: Lisi OUT Or SPIC. ConDIT104: b 07@- O t1Nf DISCMRGES TO ERvlROMRT Oy[R PAST 24 HRS. DISOWtGES TO Ixyltort9ENT OVER PA5T 24 Mits. L10i105: M GAL 5. Gross wC1/ 1 ~ LIQul05:b90 GALS.GR0552.44 Ei du ct/si T R!T! LP' wC1/mi . TRITILM3.4T f *I wCf/el GA$ti: Cit 055 N wCi/ml
  • CA5f5: GROSS ""
6.C1/m1 R.C. Drain Tk Leak Rate aos R.C. Drain Tk. Leak Rate 2*3 spa R.C. RVIA Te c. i l __ q R.C. RY1 A Terip.
  • R.C. RVIB Te o.
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f. ALES: GR OS S, _ t C ' 'm1 Pi ;, 4 s. {
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  • Cc: J R. Floyd _
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  • mC1/e1 LIQUIDS:19b). GAL 5. GA0553 *) ET wC1/ml
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  • P**S 4 m!mRT 001. SWT OF SPEC. Cr/wlil0N: PRIMART CO. GUT OF SPEC. COSiflat: -- i 1 -t. . , _ Mt f ni,ur un urt uh .:n Pa m s a u mart efSs/ sm .i SEC. Oct. (In SPEC./0UT OF SktC) 5[C. O DI. (a p /t'JT OF SPEC) ,
LIST GUT OF SPEC. CO GITIONS: Lisi 001 Or 5PEC. CDCIT!!1ts: ~ l MA ._Noor n 015060GE5 70 DITIlONENT OVER PAST 24 Mt5. 015CreicGts 70 trVikonMENT OID PAST 24 MRS. - LIQu!OS: A EALS. Ga055 # wCf/s1 LIQUIDS: QL_CALS.GA0553.Iffb sCl/m1 TRJ T!* M sti/mi .r... Pat 65ml0*L.C1/s1 . EASES: Ga055 8 eC1/e1 GA5t!.: C4055 """"' wCffel 8.C. Draf n it. Last Rate R.C. RVIA Temp. E '_7 epe R.C. Drain Tk. Leet mate t.C. RY1 A Tesp. / 7 7 . C, IM ses a. R.C. RY18 Tew . Il 1 R.C. RY18 Temp. ti'I . # LC. aV2 Tag. 'l . ~ R.C. ty2 Temp, pe , y  ; f Ameerts. Problem Arnes. Occurrences Romarts. Problemfreas. Occurnaces y and Timect and Timeclocks; i d'IA.k(s;Mc is. yaegaasi #0 -?-/>$ oos '
t. 'W G.T W -t -7.6 oos Mg~T ItayIW WCC"JT "
Anticf Mted Operations (# et N Mrs.): Anticipated Operatf oes (Nest M Nrs.): J ZuS%L4. %Snapas gl11 ton Ea11on Tank 3l Ft. FT $*,Pik7150R - Mare Distributed by 073J to f0II*9 j gir.al: 1sttchboard Opersto[, g,,,,,(ggg) h l! g yg o , f*e,c. { .. ,,, cc: C. P. Miller J. R. Floyd 11-7 5h1FT 5bPE A. Hawtins J. B. L an , .T..
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~ P0sem.,233 #'"Ga05 StTA/GA* ,2 7/ i.r e/s) ., SORONAQ CROSS LtiA/G496 19111Ith, ,1 MTE # / t'/_ff Ta ! TIIN,,_&f(,,,,i,C f /mi DAYF Cl/e1 5 I II3I h i,C1/m1 Daft a I3I 17.I4Pdi/el BAft_ f3h 'I PRIMAM Det. DUT OF SPEC. Cf/0! TIT: PRINARI CHLM, OUT OF Spit. **'.. sun: ON>Wf _. A)fnJf J/[A PRimRT LIAK RATI ". *M St C. dot. PRIMARY LfAK RATT_ . f/P GPM l /0UT or SPIC, LIST OUT OF SPEC. C0x0!i10'is: SCC. CluN. tist out or SPEC. C0c!110rts: /0UTOFSPEC) y Al0W __ --. AMNE ] 015CHA%510 titTinowfiri Ovtk PAST 24o!',*."'u",t gRS. s 70 ENVIRO'e'[NT OVER PAST 24 HRS. 'i (1QU105:163 $ _ GALS. CR055 G,$ff[Cr,m1 LIQUIDS: I.2ff"' Gats. GR055]. $wdi/m1 TalilC'_.2.Streht/al T " .**, 4 .7 Jr,e .,C1/mi GA5t$: GROSS f 7 E,a*Y_ytt/a1 .2 GASES C-1055 3. .c wp"S sci /ril - I R.C. Drain Tk. Leak Rate __ M[Ac;* R.C. PV1A Tese, R.C. Drain ik, teak RateJ. 9 0 J R. C. P'.'18 Tew:p._ R.C. RVIA Temp. jpi " -1r.ss ,.. e-- f I'.C. Rv2 Terc. F R.C. RVfB 1emp. R.C. RV2 Ters. / f) / p av_ h aemerts. Problee Arees. Occurrences *( and Tineclocks; Remarks, Probles Areas, Occurrences M and Timec10ckst Cashes ov r4 *s. wser //c-A# 00.1 h kN VlY$ A$f b S O S$/Af 00j f Artic4ated Operations (Next 24 Hes.): Antictrated Operations (Nest :'4 Hrs.): $ NRW VAteem da tu. tone C o u ro t nr fr%fse 8 n,116..* Cette*. Tark Ft. 3p1 5 - eviv;). . Have DW%ted by 000 to followiao + o.i. ' 'sitt%eard C9erato[, pg rg p g) , . . . . , . , , .. m , , . , _ _  ; '" 3 . . . o, , _ c '@l . . , . .
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m .- ^^ *' ~ . j lx*2_ - ~ + pitJggthuEAlNN.MTEl ~ u.if i~ untf it e .. ( s2 sunsp,fft/ trp0 A5 of fM te AYG. CORf SURRUPMEFPC A5 SF 3!/ 7 $ , Date i P.pt tl5 TID CANSILITY ~ We ET PJM Ll5Tt0 CAPAt!LITT $7flede ACT sed 6. P.;T - G4055 ECT ===- N OUTPUT, M l GRQ$$ KT 8Y i .n Snrta: nn. c., ar m s5uw 4lL _ mmnr Snica: Tt Ela_*r Pecs5untazer soeJ319 erT u c w M A i,Ci/mi 8080s /tM 54055 KTA/G4'm . a f L =Ct/mi l Tt1TI 1 uTI 3//T/JG TRIT!tpl__. Q S wCt/s1 WT! 2/d/M 1131 9 U r, sf.1 aAftMM 113I dA m e 4 1/mi Daft 3//J//[ permtv ChJt. GUT OF SPEC. CDN0lflog: PnTIGRT CEM. INT OF SPEC. Caub!T13: A)O Alf A)t1 A2K l mm:1 tra urf v/4 s,* Parmai tras uit . 9r een Sn.:et. @ tor 5ptC) 5tC. Can. @ouf Dr SnC) LIST DJT OF SPEC. Cohtlilous: LIST DUT OF SPEC. CouDITIONS: AA0arL n%sE CISCWEC5 70 (NYItouENT Orte PAST F4 HRS. DISChAaGts 70 DIVla0 MENT OVit PAST 24 le5. LIQUIC5: fle?/ GAL 5. Ed.39.%k) LIQUIDS: - EAL5. Git 055 - aC1/ml TRIT!P 191fmN/e1 TRITitM = wC1/s1 GASI5* Ga055' mW sci /s1 GA5th. GROSS - wC1/e1 R.C. C ain Th. Leak Rate _4/[A R.C. P.1A Tee. c;e R.C. Drain it. Luk Rate / p 1 a.C. kflA Temp. fJe R.C. P'.*18 Tees). I R.C. RY18 Teep. /J).ge/ t.C. Ri2 Tree. W a.C. att Tom . s 1.n y up homads. Probles Areas. Occurrences Ehemarts. Pre 61em Areas. Occurrences timectocks: and fleeclocis; #'E ~ //D-Pig 00$ CON Tw VC O UTe *L m gyn g Antici;4ted 0;wrations (but 24 Mrs.): Anticipated Operations (best 24 Ilrs.): IUL TALL 8 0 786. A nm.42. C * *J Yon sad 47 9/$$f l 92smasy HMusawl Ctvig 141112 . Gallt.n Tant [O rt. pjrT i.'.tkt;VA - have Distributed by CD0 to followi%: Nigirel: 1sotchboard 0;erato[, p) ..r .c.  : r. u. . ^ . o. n :.,a mw c m D.E!E . . 5 a ,,,
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'if IM/hd TK 77' 9,>. ' 7dx I: 12 dTCTT tl (. $ ' 12,o ' /0 602  ??. .;; VCTT t) 0. .'s ' 12. O ' lDb02 .j f.h: 0 G* b.'ri.*,1 K 0.i' I: C' " 380 ' j ,it > k S,l'i' FJ3' /a (, ' g ,*55 17+? ).s ~},? t,[ l -l I mi Y o' l  ?  ? .,a .. ..n.. . ..=_..._ . . . .. y L kbSXh yet p& f 44f . ...t . , g v.. ... . gn M t O ", , . f[ 4 A d ~fa x > .6 M les  :- @A /Yt/-W4 A, J. sl<<r .c.ee ~. .eka,r.- ~ M AS Mf-V22A { ..M .#A w , e . .J e 8)NITI:D OTKI ES NUut.E/,R HLNULXi ORY tN'.tMiWo.,nl RULES and REGULATIONS TITI.E 10, CHAPTER 1, CODE OF FEDERAL. REGULATIONS-ENERGY l i PART oomasue acensina or rnooucTiou ^"D UTIUZATION FACluTIES* j 50 l 'CENERAL PROVislONS ISSUANCE LIMITATIONS. AND CONDITIONS Appendia C-A Ouide for one Finenetal Data and Related Information Required to Es. OF LICENSES AND CONSTRUCTION PERMITS i Sec. - tabbsh Financial Qualifications for Facd. 50.1 Basia, purpose, and procedures oppu. 50.50 lesuance of Mcenses and construction 4ty Constructaen Pernuts and Oprating cable. permits. bcenses $ 0.3 Definitions. $<0.51 Duration of license, renewel. Appendis E-Emergency P:sas f'or Production 30.3 Int er pr et a tions. $ 0.5 3 - Combining licenses. and Utihaation feeditsee 5 0.e Co m m unic.a tions. 30.33 Jurisdictional limitations. . Appendis F-Policy 8tsisting to the S. ting of $0.$ e Condstions of beanses. Fuel Reprocessing Plants and Ratated i EQUIREMENT OF LICENSE. EXCEPTIONS $ 0.5 5 Conditaons it construction perauts. . Wute Management Facahties - 90.5 5e Codes and standards. Appendia G-Frecture Toughness Requirements 5 0.10 ljcense requared. . 50.$ 5h Conditsons of construction permita Appongs: g.peecto, Vaaset Material Surveu-5 0 .11 Esceptions and esemptions from 5- and operating Ucenses pertaitilng to sat 6 tence Prooram Requirements consing requirernents. trust matters. Appeedis I-Rumerecal Guides for Design 06 i 5 0.12 Specaric esemptions. 50.56 Conversion of construction permit tC isctives and Lasuting Conditions for Oper. j 5 0.13 Mtscks and destructive acts by ene- lacanse; of amendment of bcense. etion to Meet the Critetson "As Low As 1 rruts of the United sates; and defense 50.s7 hsusace of operating licenses. . Practicable" for Radioactive Matertalin actotties. 50.58 Hearings and es' port of the Advisory Light Weter Cooled Nucleet Power Reesto 1 Comeruttee on Reactot Safeguards. Effluents CLA551F1 CATION AND DESCRIPTION OF 50.s e Authorisassoa of changes. tests sad Appendis 1-Primary Reactor Containment LICLNSES espettments. Laak63e Testtag for Water Cooled Power I $0.30 Two classes of beensee. INSPECTIONS RECORDS, REP 0RTS appefdSa NFCCS Evaluation Models 50.31 Class tea hcenses; for medical therspy and maarch and devoto ment facibites. Appendas L-inforrsation Requested by the At 50.70 Inspections, torney Generet for Antitrust Review of i $ 0.3 3 Class 103 heenses or commercial ar.d 50.78 . Maintensase of records, snaking of Feshay Licenas Applications  ! andustrial faciaties. reports. 50.33 Construction permits. Appendia M, og .Sandardisation g of,D,esign,; g ,. cManu a APPLICATIONS FOR LICENSES. FORM. RJGHTS-SURRENDER OF LICENSES CONTE NTS. INELIGIBILITY OF CER1 A!a1 ,Reac,to,rs ,,,, g; ,M,a,nu,factured , Pwsuant to Com-APP LIC AN TS S0.30 Transfer of licenses. Appendia N-Standardization of Nuclear Po== l $0.88 Deditor regulations. plant Designst Ucenses to Construct and l 50.30cath et Filing of oppuestices foe licenses: 50.83 Appuestions for termination of M* Operate Nuclear Power Reactors of Dupt I
affirmation. senosa. ste Desi et Multiple Sales
.3 etion op t n. AMENDMENT OF LICENSE OR CONSTRUC. ^'TeNew of 'S Yagns $ 0.3 3 Contents of apphcationst general in. TION PERMIT AT REQUEST OF HOLDER frematen. Appendis Q-Preapphcotion Early Review of i 80.3 3e Mfarmetlee rougulred for astia 50.90 Application for amendment of Ucense Site SuitebiEty lasues miset actew. A .0.n Contents of a,,.cet.o. technic.i ,0..Ior sons.tructson pern.ut.is uance of e.n ndrne.t. 0,..ttr,a,rn,ar,r,t,t S.e.s.s. . , . .. . M.100.,104, as acosodedlet leis.183.,88 .3 . SiM. . n33 SS NO,3 $ 0.3 obsectives for equipment to REVOCATION. SUSPENSION, MODIFICA. g g gg Igg tuttsi releases of radioactive maternal an
  • C
  • i TION. AMENDMENT OF LICENSES AND Eff1=exts nuclear power reactors. CONSTRUCTION PERMITS. EMERGENCY tmlem othervlas noted. Secuene M Ob40 81 -]
$0.3 5 lasusace of construction permits. OPERATIONS SY THE COMMISSION also leeued under sec.104. es Stat. 9M. as i 30.36 Technical specifications, aseended: 43 UJ.C. 3334. Sectione 30.100-50.3ea Technical specifications on efftvents 30J00 Revocation, suspenason, noodificesson 80.10e tsoued under sec.108,88 Stat. DSS; 43 festa sueleer power reactors. of Mcenese end construction petsnets for USC. 3338. Per the purposes of sec. 333, 80 1 i SS.31 Agreement heuting accom to Re. muss. 3 sat: Det, as amendeda 42 US C. 3373, t 40.M a I strictes Data. 30 jet Rotatsag poseentoa of specast no. (1) teoued under sec. lett. 88 Stat. M0; 43 S0.36 ineugtburty of certain applicants. etser materteL UA C. 3301(l), and - 96 90.70-80.71 leeued 30.39 Pubec inspection of appbcations. 50J03 Comnuassos ordet foe operation affet undetsec. 1810. 88 Stat. 980, se acnended. 43 STAND ARDS FOR LICENSES AND CON- 50J0s a 'emos and operation in war er UAC. 3Mim and the h memd to la nationst emergency. APPasdices, STRUCTION PERMITS essresas peovtalons " W Beale, purpose. and procedures Ad hEalYeNerds for eines 40d m. apphesh l c$nees. so.10, geckfit ting, 84.43 Addit 6onal etsneerds for cleas los u* * 'nne regulat10ns its this part are pro-j 80.43 Additional standates and provtsione effecting che los beenees for commercial so.t:0 Wissions. ' h Cornenteston sandsstedpursuant bF theto Weh W6tm the Atocnic En. l g is, ergy Act of 1964, as sinended. ($$ Stat. S O Afo**'. andards for Econnes authertains es* APfENDICES p 9191 and Titles II Of the Energy Reor. ranisation Act of 19'l4 (88 Stat.12421 to 50.af g'c'eI' ' 8044 As Nce N"[f"afer*ieNcf r A'P',*$, dags[a Crm kr Nu. provide for the Ucenstz:s of product 100 **r* eoclang arrtems for baht water no. 3 Appendia S-Quauty Aaswance Criterne for No. and ut11116t10n facilities. * **' 8' **' '** Ci o'8. eteet Powse Plants and Fust Repeoceming "* N' . 'Astradtd 43 FR etIs. 504 September 1,1978
.. . _ _ _ _ _ _ _ _ J
l c~.m .4 a i o.mu Lw.w.0 er muwu m o a..a u num u um t,.; I l enmponetta of boul:2g and preuurized (U Curwtructson of r on aucht fae activities should be continued, pending j uster-cocJed nucle ar power reactors,  !!ues (such ea turbo.renarstors and the tuuance of a construccon permit, J such as pressure veuels, piping, pumps, tuitune buildJngs) ami teroporary build. notwithstanding the profluona of para.  ! and valves, which are: inas (seeb as construcuon equJpment graph (c) of this section. If such written (!! Part of the reactor coolant system, sWade sheda) f e uaa in connecuen with statement has been submitted within the conatruccon of the facility; and the time specified. such activides may n (4) W!th respect to production or ) ,(2) Connected to the reactor coolant n uultrauon fac1 Hues, other than testing continue to be conducted pending Com. mtulon accon pursuant to subparagraph arstem. of Up to and including any and aDsuant the foUcwing: @* faculues. to secuon 104required to beIM
a. or secuon Heenaed
e. of pur.(2) of this paragraph (d).
(1) The outermost containmerit isola, ,, the Act, the construccon of buudings (2) Upm submissim of a statement tion valve in system piping which pene, e which will be used for acurtues other of reasons pursuant to subparagraph (1) than opersuon of a facDity and which cd this paragraph (d), the Comrrtulon trates primary reactor containment, may also be used to house a f aculty. (For may author.ze a the continued conduct of (U) Th2 second of two valees normaDF essmale, the construccon of a cohere activtues permitted by paragraph (b) t ebed during normal reactor opersuon laboratory building wita space far in. of this seccon in effect prior to (efree. in systern piping which does not pene. stallauon af a training reactor is not tire date of these amendments), upon trate primary reactor containment, agected by this paragraph.) conalderation and balancing of the fol. (111) Ths reactor coolant system safety - loving factors' and nue! valna. This paragraph does not k (D Whether conttnusuon of the ac. For nuclear power resetors of the dirtet [ ly to production or ututzstion facua. ia tivities viu give rise to a s cycle boiling water type, the reactor cool. 3 ap c.nt systern extends to and includes the S g ties subject to paragraph (c) of this CI the verse impact nature and onextent the environment of such impact, and section. outermost containment inciation valve in " if any' 5 th3 main steam and feedwater piping, ( ~ gQg g (c) Notwithstanding the prortstons of anvironmenta! !mpact frocn continusuon (w) " Administration" means the En. paragraph (b) of this section and sub. of the acuvides can renamably be ergy Research and Development Admin. ject to paragraphs (d) and (e) of this etrected should such redress be neceuary; tstration or its duly authorized section, no person shal} effect commence. (111) Whether continuscon of the ' representr.tives. nient of construction of a produetton or activities would foreclose sub6equent adopus of alternatives; and ! 8 utuusta)n facility subject to the provuions of C o 151.5(s)" of this chapter on a sats on which (17) The effect of delay in conducting j 1503 Interprefafsons. Except as tpe. 2 such activiues m the public interest, cifically authorized by the Commission in e the facility la to be operated until a con. Including the power needs to be served e rtting. no interpretation of the meaning *d struction permit has been tsaued. As used by the proposed facility, the avaus.bL11ty of the regulat;ons to this part b* any
  • in this paragraph, the term "commente. of alternaute sources, if any, to meet odcer or employee of the Commtssion ment of construction" means any clear. those needs on a timely baJ!a, and delay i other than a written interpretatlun by ing of land, excavation or other substan. costa to the applicant and to consumers. I the General Couruel sill be reccgruzed tial action that wou2d adversely afect (3) Activittee permitted to be con. j to be binding upon the Commtuton the environment of a site, but does not tinued pursuant to this pararuph id)
. mean: she.U be conducted in such a manner as 3 50.4 Co mm u nica tior... - ~ wiu mmimtu or reduce their environ. Except where otherwise spectned, e.11 (1) Cha.nres desirable for tbs tem. ,menta! Lmpact. com.munications and reports concerning porar7 use of the land for public recrea* (vHI) The Directo' of Nuclear Reactor the regulations in this part should be tional uses, necessary borings to deter
  • Regulation may authorue an spphesnt for s  !
,nine foundation condluons or other pre. addreued to the Director of Nuclear Re. construcuon pernut for s utilization facabty l stor Reguistica. U.S. Nuclear Regula. co o which as subject to i S t.5(s) of thts chapter, j d gory ComtrAston. Washington, D C. s itabluty of the rite or to the protec. and is or the type spenfled m Il 50,21(b) l .0553, or may be delivered in person && (2) or (3) or 50.22 or is a tearing facilayt to con of envirremental values: the Commlulon's omces at 1717 H StreA (3) Procurement or manufacture of conduct the followins setivw NW., Washir ston, D C. or at 7920 Norfout components of the facility: and t!es: (1) Prepantion of the sita for con. venue, Bethe sd a, Maryland. (3) With respect to produccon or C1 struction of the facility (including such 111ation facilities, other than testing is. actsvitsee a ciearing, grading, constrte. s tem us ant or ucawss. ExcarT1ons cilluce, required to be ucensed pursuant tion of temporary secesa roads and tw,r. I 50 10 Ucewe required (s>Escept as to sectima 104a or seccon 104c of the Act, row aresa); (til installation of temporary provided to ( $411, no person within the the constructicas of ba13 dings which grill construction support faciuties (including United States shall transfer or recette u. be used for activttles other than opera. such items sa warehouse and shop f acitt. La tntersLate eommeree manufacture. E tion of a faciltty and which mmy aho be tjea, utilities, concrete mtriny plan ts, produce, transfer. sequve, po.ueu. or uwt any '8 doca.tng and unloading f aciuties, and pf cductJon or used to house of the construction a faciuty, a Couegs (For eatmple, h ConstrVetion support laboratory IHd1A f rign ) ; t Lij ) uullntion factitty except s.s authortted u, a buildmg with space fos"instaUadon of a 3 eJLcavauon for facility structures; (iv) by a Licarue tasued by the Commasion. " traMmg reactor is not afected by this g construction of servios facilities (includ. pragraph,)
  • ing such facilities as roadways, paving,
,, (b) Na person shan begin the con. (d) (1) Farh person subject to the R railroad spurs, fencing, exterior utility stry llon cf S producuon or utL112.ation provisions of paragraph (c) of this sec. and lighting systems, transmielen lines, fictllty on a site on which the f act!!ty is tion, who is, on (e!!ective date of these and sanitary sewerage treatment facili. to be operated until a construction per. amendments), conducting activities per. t!es): and (v) the construction of strue. Init has been lasued. As used in this pa f a. mitted pursuant to paragraph (b) of tures, systems, and components whJch aruph, the term " construct!on" shall bs this sectbn in effect priot to March 21,1972,* do not prevent or mitigste the conwquences of detmed to triclude pouring the founds. enay furnish to the Comnussion wiOus 30 days postutsted scodents that could cauw undue tion for. or the installation of. any ter. after March 21 f972 ' of risk to the hestth and safety of the public.t No tion of the permanent f acility on the such later date as may be approved by such suthortaanon shsL1 be gra.nted unneu the site, but does not include: the Comminton upon good cause shown, til $1t3 erplorstloc, site excavadon- start has completed a final ennronmentalim-a written statement of Say reasoca, with prorstion of the alte for construction poet statement on the issuance of the contirue-supporting f actual submhalon, why, with con permet as required by Part 51 of this of the f acijlty, including the driving of reference to the factors stated in sub. puet and cetruction of roadways. rail. paragraph (2) of this paragraph (d), the cha pter. "out spurs, and transmtulon unes; (2) Such an authorization shall be granted only 4.fter the prealding oScer (31 Procurement er mr.nuf acture of .t.rfective oats of triese a mendments. In the proceeding on the construcUon comoonants of the f aciuty; " A/ne nde d 3e F R 2 42 7e. permit applicadon (1) has made all the t Amended 42 FR 22882. flodangs requued by 151.52(b) anG (c)** of 8 Amenced 43 FR 6e t s. thas chapter to 50 3 September 1,1978 PART 50 e DOMESVC LICENSING OF PP.ODUCTION AND U nuzAlluN I AC. .s&S At the presosed lodation without undue etsk to the health and safety of the public. frars! whos na spyttesnt has evpptted ( tatually su of the technjcal informados sequued to campiste the applicatfoagud. Ine the Anal destemis tAe f aculty, tan and., Laes toq1aued above win be appropriately, escruAee to annect that tast (b) A construction permit will consti-tute an cuthoritadon to the applicant to proceed with construction but wGl not - constitute Commission approval of the safety cf any design feature or specifica. t!on unless the appucant specifically re-questa such approval and such approval !a incorporated in the permit. The app 11-cant, r,t his opuon. may request such approvals in the construction permit or. from time to time, by amendment of his - coratructics permit. The Commission l Eay,in lts diacretion. incorporate in any' construction permit provisions requir.' ing the app!! cant to furtusa pedodic reporta cf the progress and results of resecrch and development programs de-ped to resolve safety quesuona, (c) Any construetan permit wt!! he subject to the limitation that a licensei cuthortzing operation of the facility wiu .not be lasped by the Cnmmwon untu ,1) ( the cpplicant has sutnnitted to the Commtutort, by amendment to the ap- . PI!e*tlon. . the complete final safety anal. i 351s report. portions of which may be
  • submitted and evaluated fzt.m time to
. time, an3 (2) the Commwon baa fougd th:1 t.he final design provides reasonable Msurance that the health and refety of' the pubile wul not be "endangtred br operation of the f acil!ty in accordance. with the requirements of the Ucense and the regul-uena in this cbspter. G 50.36 Techa cal specifications, (f.) Each applicant for a license su. thorising cperauen of a production or c*."tt.auo3 facility aball include in his tpplicautn proposed technical specifica. Aloc.s la secordance with the require. + menta of this secuon. A summary state. ment of the basse or reasons for such ' specifle:11:ns other than those cover. l Ing administrsure controls, aban also be included in the applicauon, but shall not become part of the technical specificattna. . . .; (b) Eac1: ticense authortains opers- . tion of a produeuen or uullaauon facc. tty of a type described in 150J1 or ' I 60.22 will lacInde technical specioca. tions. The technical specificauons will be derived from the analyses and eval-untion included in the safety analysta report, and amendments thereto, sub-( . . ... u 1 1snt , PART 50 e DOMESTIC UCENSING LF PRODUCIION AND OTIUZATION FAC!u s ms y mitted pursuant to I ou 34. The Com. before a sMety t.imit is exceeded. If. dur. I or in accordance with the requirements . mission may include such additional ing operation, the automauc alarm or ,8 of this part in effect priot to January 10, technical spect'leations as the Commis. protective devices do not function as re. - 19G9. zion Ands appropriate. Quired, the hcame shad take appro. 3 (3) At the laittauve of the Commis. priate action to Inalntain the TwisNes "" (c) Technical afwinraetons will in. within the nmiting eantro!. setting values [**emended slon or the  !!censee, to include any license technical may be scecifica. cJude items in the fouoving ca&aeories: and to repair petmaptly the automaue e tions of the scope and content wnich (1) Sa/eJr limits. Idealtina as/ety sys. fem settises, and IlmJiana control set. devices of ce to the process and.ahmt downto the If required shut aSected part being 1"ued. "{would be required if a new Ilc firws. (D (A) Safety limits for nuclear down h en&Lre process for repair of ,,, reactom are limita upon importan& antesnatic devices ne Ibenase shan no. g 30.& Taksical spal6ce:1.n en ef. procams variables which an found to be tify the Commtantan, rettew the mauer. A.cnia fr ,es e ei.. , p .. ,r,sei m . and recorit the resulte of the review,in. ' necassary to raaaaaahly protect the to. (a) In order to keeD rel ' j tegrity of omrtain of the physical bar. cindtag the cause of the condition' and ,,gg ,,gg, g, [ff*dI*" ' riste which guard against the uneen. the beste for corrective action taken to during normal reactor operadons in I troDed relenae of rahirtty. If any preelude reoccurnace. cludins eWed wrauonal occur. ! safsty limil la evandad the reactor shan (2) Lindfana conditions fJr operstfos. unces.as to= ss is rassonsbh schicsNe
  • each l be shut down. De "r-a= shan nouty Limiting condluons for operauon are the the Commianha netew the matser and lowest functions! capability or perform. 3,',',*,"d*,**,N,",Q*['g*,7,"j,',*n"n",',$,'g,','*
record the resuHe af the review. includ. ce ance levets of equtpment required for e in addinon to reau riris complisace mth appu. ing the cause of the condauen and t.be E safe operation of the facility. When a acable ptonssons or $ 2oJ oe or sh i chspier* basis for corrective action taken to pre.
  • Itatting condition for operation of a nu. $,, gun, .
' clude reoccurrence. OperatJos shan not Iclear reeeler is met met, the thensee (D That operating procedures devel. be resumed until aut%rtsed by the shan shut dews the reactor er fotow any oped pursuant to I 50.34s te) for the con. rwwcn. rbmadf a1 acuan permitted by the techna. ca! specification unta the condition ca.n trol of emuents be established and fol. (B) Safety !!msta for fuel reproceas. be met. When a Itmfting condttian for loved and that equipment instaued in lag plante are thone bounds within operation af any process seep in the sys. the d scun waste system, pursuant which the procese variables must be gl a(a) W mamed and used. teso of a fuel norossasing plant is not , maintained for adequate control of the - operstion and which murt not be es. met, the 1scezues shan shut down that "" (2) The submission of a report to the ceeded in order to protect the integrity part of the opersttoet or foDow any n. appropnate NRC Regional 021ce shown of the physical system which is deslaned usedini action permttted by thes ehnical in AppeMix D of Part 20 of this chapter to guard asc.tnst the uncontroUed release spectScattan until the condition can be within $sxty 880) days af ter Janua 1 of radidacthtty. If any safety Itmit for met., ItL the came of either a nuclear nac. and July 1 of each year specifymg the a faut reprocessing phet to exceeded tot or a fuel reprocessing plant, the IJ. quantity of each of the princinal redio. cornettn action shad be taken as stated cansee than poUfy the Commtantan, re, in the lectmleu! spectScaMon er 1.be af. view the matter, and record the resulta g nuclides released to unrestricted creas in fected part of the procesa, or the enttre of the review. including the cause of the e liquid and Jn gaseous emuents durms the procesa If required, aban be shut down, candluon and the basis for correcuve - previous six e61 months of operation, aetian taken to preclude reoccurnnes. E and such other information as may be unless such setian toald furthat reduce required by the Commission to estimate the mar:1L of safety. The licensee shall ,,,, notif.7 Las h=' don, review the mat. (3) Surveillance requhements. surveil.' martmum potential annual radistion ter and record the results of the review. lance requirements are sequiremente re. doses to the public resulung from e5uent including the came of the condition and latics to test. cabbration, or inspection releases. Copies of such report shau be ths be.sts for corrective action taken to to assure that the necessary quality of sent to the Director of Inspecuon and preclude reoccurrence. If a portion of systerns and components is m31ntained. Enforcement. U.S. Nuclear Regulatory the procas or the entire proeves has bun that facility operation willlie within the Commission' Washington. D C. 20555' CDut down, operstfon shad not be n* safety 111 nits, and that the 11rniting cen. ::: sumed untG authorised Ity the Cctsm.is* Il quanutfes of dations of operation wiu be met. radioactive materials released during the h its Despn /cotres Design features nporting period are signiScandy abon tu)W Muos safety systent set
  • to be included are thoke features of the destan objecuves, the report sha11 cover I*' "" ""CI"" "" SU"8' facility such as materials of construe. this apectScany. On the basis of such n.
I*' ""*'"*"I* P"*"'3" 8'"*" "I*I*# tion and geometric nrtnngements which GD those variables latring signifkant ports and any additional tnformauon the if alteled or modifled would 'have a sa My funeWas. h a uminng safety significant eifect on safety and are not Commlaston may obtain from the 11 *""
  • P' covered in categories deberit.ed in sub. eensee or others the Commission may
$ ch a safety un the setttng shad be no chosen that auto, paragraphs W.126 and W d this ha Me to ume nquin the UunsM mauc prosecuve action trtu coatect the ; paragraph (c). to take such acuon as the Commission aboarmal situnuon before a safety Haig , (S t. Administraffte controls. Admirus. deems appropriate. {D escoeded. If, during opersuon. the a trative controls are the provisions relat* fb) In establishing and implemenung natoenatic safety system does not fune, aing to organization and management, the operating procedures described in Men as nquired. the Bcenaee shan take g procedures, recordkeeping, rettes and pa ph W M M ucum W UN Appropriate action, which may include audit. and reporting necessary to assure s Chutting down the reactor. He shan ne, operation of the facility La a sah e ee shaU be guided by the following con.
  • sideratiorw Experience with the design.
ma r.ner, g Idli11 This arction shau not be deemed *c GEy the Commtanian review the matter 'ucth ud muon of nuh C9d record the results of the review. In. to modify the trehntent specifications in. $ power Gluding the cause of the condition and withreactors and! cates the techrdcol that comphance specifications de. the beels for correcure acuan taken to cluded in any Deense imed prior to Jan. ee,.lbed in this secuon wul keep average da noccurnnee. uary 16.1969. A license in which technt. annual releaste of radioactive material G) Ilmiting coctrol settings for' fuel cai specifientions harc nnt hMn dests. An eSuents at smau percentages of the Wprocessing plante an astungs for Mated armil be deemed to include the limits spec 1Aed in i 20.104 of this chapter Outomaue alarm or protocuve devices eure safety analysis report as technical &nd in the operating Ucense. At the same plated to those variables having sign 1A* speetticattorw tune, the 1:censee is permitted the flert. cant safety funcuona. Where a limiting (2) An applicant for a license author. bility of operation, compatible with con. G2r. trol sett. tag is spectaed for a variable 1*Jng operation of a prnduction or uttit. siderettoris of health and safety, to as. G3 shich a e&fety limit has been placed. nation f acility to enem a cont.trucuon sure that the public is provided a depend. peimit has been 1.aued prior to Jan. able source of power even under unusual the tactivesetung shau action, be ao either chosen that automaue pro". or man operating conditions which may tempo. uary 10.19f 9 mny mornit technical t. nee. ual, sul correct the sbnormal situnuon aficaitt ns in acenronnee with than petton. rarily result in releases hasher then ruch a Amendee 4o tit seset. September 1,1978 i 1 e PART 50 o DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FA -, ene,rm, ,sio t,.,m,,,,,,o, of.po.., from a. transmianon nei.oa. o, rf f,- c,c.oi,,voa ofu,a:-o pwom r= b = 8 for p,eersio. ,,),,,,o,,,, o,e, o,1,o t ,,,c,g a . ion,of po. r . pu,0.n from ae on.ae etemne es,, ,,,,,o,,a,tabies an,d ,ne. sirveturn y.. cety a,,t,y meatauon to ,,,t,m, a,u,t. - ema. and componen a tmpeme. io ,ang es o, no,m u o,e,ecos ,o, CHf4Hoss 38-f a*paction end testing of man be doigud io withmed a eeni. of, ,atedas earthquat" n s ottelpated operational occurrences. afsetrteel end for poseer systssa. Electits po*atsys. esturel phenomena such cornadoes, hurricanee. Sooda, tems imporunt to esfety mBall be designed CMcBee witbout loss oftsunam!. espabultyand" adequate to perform 'atfety, %including accident those variables condluona as to permat appropriateappropriatetoperiodic assure inspection and
thett safety functions, he design bases for aC and systems that can afect the fleston proe.testsfit of
,these structurve, erstems, and cornpocenta h ans. the lategrtly of the reactor core. the lEnportant artaa and feature 6 Such ta wiring'. Chall refect: (1) Appropc14to cons!deration k reactof eontainer.entcoolantandpressure boundary, Sta sanoctated systemaaud the Ap. taau'.ation. connections, and switchboard 4 cf the moet severe of the natural phenomena to aaness tbo conttaulty of the systema and that kan been Womany Mported for the proprtate controLa shall be provided to realn. ,he conditton of thett componenta. The sys. alta and surreanding area, with SulBelent tain these tartablee sad syste ms erit 2Wa tegna aba5 be Gesigned With a capability to Inargta fit the %Linited accuracy. quantity. PMacttbed operating FEngen. . test periodicany (1) the operabittty and and perted of accuenulated. time La which(3)the histortcal E e48erson 144eactor snowrms pressure funstlocal perforunoe of the enmponente dzta bafe been appropriate gr pressure of the systerna. suc hd as euo,nett.e. ,e, .power ecurces; ,,3 13,o , combination of the efects of normal and boundacy. u s,y .The ail reactor . de, ,, ,,d, coolanty..,t,, t,d, , i.,e. ,,ttenes, accident eoadations with the erects of the goo erected. and tested to as to here sa arttemely erability of the efeteens se a whole end. under natural phenomena sad (3) the 6mportance enadiuona se elene M og as pracuct ue * *> r >~ s *** < u = - +< - >= ~~~ a-a = *r= ne r - of the safety functsons to be performed. W probabtuty of abnormal ledage, of lesna inte operatton, including operation of ,," !."'Voom'%/a.'Crtaa?.'arI rupture. applicable porttoes of the protectio.n system,. aba0 be designed and lottled to futalanise* Cruertest 15-Seactor coolent eyetem de. and th. 4,n-fer af ,own amon, t 4 nucies we rescar cooiani .y. tem and es.o. a =l; g ,a, n g ",ar,o ali f a,,=,a y; ei, elated aunttiary, control, and protecuon sys. l# 'I ##I E power unit. the oestte power erstem, and the ' P ' ' ~ plastor,a. Pfencombustibts and heet resistans '* *8 ** ' I #8 $8 Crtiertoe 29-Conf rof resist. A controt room Insteriale 8 ball be used wherever profilCal to assun that the destgu eendfu'*ons of t.be 8 bah be PWided fits which acMn3 can be *nroughout the unit particularly in loca. MacW ecotant PNae#e boundary aM not ===a anfety = a *paaa = mi~ *~er ==a tiene .such =~*d surl=s =r ana2noa or under norinal conditions and to main. n,easetacuon the containenent od aghun an,dsymma control operation, including anticipated operauonal tais it in a safe condluon under accident af appropriate espacity and capabiuty ansJi eaurnaces. conditions. Including leas.cf. coolant acct. be provided and dee;gned to sninimise the ad. Crtiertog 16.-Conte (ament deetpt. Steac. dents. Adequate radiation protection shall be eersa efect.s of Sree on structures. erstems. ter contalhrnett and associated systems tha11 provided to percut access and occupavy of add Componecta important to esftty. Ptre, be protMed to estahtlah an cementially leag, the control room tander accident Conditions Oghting systetna abau be destgned to assure tight barrier against the uncontro!!ad to. without penonnel recetting radiation es. that their rupture or inadvertent opereuen lease of redloactitity to the environment and posures la escene of S ram whole body, or does not signi$ car.tly stopMr the Galsty Cape. to assure that the containment design con. 14e equivalent to any part of the body, for bluty af these structures, systerns. and ditione Important to safety are not es. the duration of the accident. j componesta, coeded for as long as postulated accideng Equipment at appropriate locattens out. Crttactos d--gnetroementar sad missite de. sendittona roquin. side m control room thall be prortded (1) sty's bases Structures, erstems sad com. with a design capabLlity f or prompt hot sbut. ponenta impcriant to safety aball be destgoed ; Criierton Jy-ffeef rie power systsmJ An down of the reactor. tactuding necessary i to seccmmodate the ef ects of and to be com. onstte electric power system and an offstte Instrumentation and conttets to autaton pattble with the entrionmental conditions electtte power system shall be provided to u. the unit in a safe condition during bot abut. maaociated with nortrat optratien. staante. pertnit functiomas of structures. systems, g down, and (3) w1*.h a potentia.1 capat Utty testing and postulated acetdent.s in. and cotoponents important to a&fety. The n for subsequena cold shutdown of the reactor nance's boas-of coetant accidents ThesesMety function for each erstem fas.surning { Wough the use of autta'ote procedures, cludin strictures. systems, and components aball be the other synem is not functioning) thalt tse appropriately protected against dynamic af. to prof tdo suScient capacity and cepsbility fil. Prostrt40s and Jtsacffttfy Coiifrof f acts, incluiting tbo efects of stasites. pipe to nasure that (l) epectaed acceptable futt $ g p g ,,, ebipptng, and discharging Bujdt that may deelFn limit.s and design conditions of the Crtftrson 20-Protertion sys(cas funcffo% result frotn equipment failures and from reactor coolans pressure Doundary are not The protection system shall be designed (1) e=ents and condatlons outMde the nuclear enceeded as a result of antactpat.ed opers. to inatiats automatteauy the opersuon of power unit. tional occurrences and (3) the core La eccled approprsata pretems including the reactivity .- and containment integrity and other estal control syste;us, to maaurs that speel8e4 ac. Crtireton 5-34act of eteuctures. systema
  • functions are anstatained in the event of ceptable fuel design itinita are not exceeded end components. Structures, eyetems, and postulated accidenta as a result of saucipated operational oc.
ecmponenta important to safety aball not be he onette electric power supplien. IAclud. currences and (2) to sense sectdent cond1 abared among nuclear power units unless it ing the batteries. and the onalte electrie tions and to inttaste the operation of systems , can be abown that such abaring wiu not etg. distflbuuon system, abatt fieve auscient and components tmportant to amtety. al$cantly tImpair bett abutty to perfonn , Ladependence. redundancy, and testability to Crissinos 21-prottetson system ref'sP (if ty .. thelr edety functions. Lacauding.ta tbe scent perfortn their safety functions assuming a and issteDellfy. De protection systert shs:1 of na accident in one unJt, an ortlerty abute sangte la Aure. be dest (ned for high functional renabluty down and Cecidown of the reMning ualta. r Electrte power from the transalaston net. sad laservlos testabtitty commensurate with ' fas wore to the enatte electrie distribution the safety funcuens to be performed ste. = dundaney sad tacependem demped tato ff. Prefecison Dr == =Maltfpid Feaston m u ependen Prodseg i,c  ; erotem m fact abau a.cosaarur b.e s.upplied on the proteetton by two systern payascastyshall be sufbclent to **parete rights of way) designed and located easm that W me dagte faum Moulte in Crilenos 16.4teactor desten The reactor fi e as to nuounime to the emot practical tae lone of the protection functnen ased (9) re. more and name n ted coolant, onstrot, and likelthood of thett almu!Laneous fauure trader anotal from eerneo of may component or ' protection eyetama aball be desagned with operaung and postulated seciernt and es. ehannel does act resull La loss of the re. j appropriate margta to amaure that spedAed etroamental condit$ons. A twitchyard corn. 8.utred sninteuas redundancy unless the ac. i teceptable fuet desten limits are act es. mon to both ctreutta le acceptable Each of wptable rouabutty of operation of the e**ded during any conditten of normal op. taene circutta shall be deeJgned to be aven. protectica eyinem can be otherwise demon. , ersuon. Lactuding the egocte of anticipat.e4 ante la suJtetent time following a toen of au strated. The protection system aball be de. l i eperettonal occurrences. onstte alternastng current power supplies a&gned to permit period 14 testing of its fune. ! Criterton JJ-Asector isAerent prodeertest, and the othee o8atte electric power carrutt, Stoains when the reactor to na operatiert. ' he reactor erre and associated ecotant aya. to aezm that spectSed acceptable fuel de. aneluding a espabuny la test ebannels nn. tetna sball be dentyned so that m the power alta une and design oondmons of the re. dependently to determina fattures and lenses eperating rangi the net efect of the prtunpt actor coolant pressure boundary are not of redundamey that may have occurred, N inherent auctest feedback charactertsstes encoeded. One of these streults saalt be de. Crfiereon 334rotectton systeam independ. tends to actopeasate for a rapid increase la eagned to be avatlable witata a few seconds ,mee. The protection system aball be 6e. ' reactietty fecowing a lens.of.coolans acetdent so samure siso d io aneure that tbe esects of natura Cntretch 12-Juppresston of reactor powe, ** = cauns *==$=:a= eat 8=$*griir. ad Phenostema, and el normal operaMs. ena!n. .seoiseim ha reuser core and osociated 9 ber ettal esfety functiona are maintstood., anano, insting and posiuist, accidens ! eholant, control, and protecQon Syntama aball Pr****' *bau be included to minims, *caditione os redu&daat c h an. 's do not be destrued to masure that power occittauons the probabluty of tostog electric power from resu21 in toes of the protection f neuen, or whar.h can result ta conditione eseceding any of the reinstatng supplies as a result of, abau be demonstrated to be ecceptable on i spect6ed acceptable ruet design LLmnte are or autocident with, the naas of power gen. some otner defLned nuts Design techaques. l mot poestbte or seu be sentably and reedity ersted by the nuclear power unts the sees auch as functional stearsity or (11versity la l est,eud and ,upp,e e,( 6 .. .y j I bW W 9 O G.e'*.3t i N 1. m c r..s.i w L o t 4.i. t,c ;su s n sti y 3,(.,a ...u ,e c,,s.; ,s; n.., ,mponent design and prtnefples of opera. IF. fluid Systems for ossite electric pcwor systern of eretton on. shall be used to the estant practical to Crtterfon J0-4.elfty of reactor coolant (saauming ocante po*er is not avaMst.e) th e . event loss of the protection funetton, presskre 4,emndary. Ccmponents which are synem safer funcuan can be acccmpust.ed. Criterton 2NPr otection aye rem /eflues part of the reactor coelant pressure boundary assurrung a sirigle f ai;ure. odes. The protection eystem shall be de* ebau be da 1gned, fabricated, erected, and Crftenom Jbla spection of e m e p e'i ty gned to f.il tuto a sale state or into a state
monstrated to be acceptable on some other teeted to the highest quauty standards prac.
(1 cal. Mesna sbau be provided for detecting core so timp systens. N ernergency core caoung system shall be desigted to perml( ] .ftstd basu if concluono such as discon. and, to the asuns pracucal, identifying the approposu periodic inspection of irr puntantt
ction of the system, loss of energy (e g.
location of the source of reactor coo ant components, mh as sprey mgs in W tortor ectric power, Instrument str), oe postulated leakage, pressure eensel, water lajection coules. and  ; terse environment leg., ertMme best se Crstenos JJ-practure prevention of re. piping. to assure the lategrity and capaD111ty -14. firs. pressure, steam, water, and radja. actor coolant pressure boundary. The reacto, of the a, statn. on) ars experienced-sociant pressure boundary shall be designed Criterson Jf-Taetimp of evrtretMey core i Criterion 243cperetton of profeefios and with sufBdent snargtn to assure that wtan ecoung naten De enginey core cWing } nirof eystema. 'Jhe protection eyetem shall strassed under operating, maintenance, test. system anal! be destgsed to pernut appro. eeparated from control eyetema to the es. Ing, and postulated socident eend!tions (1) priate periodic pressure and functional test. It that faMure of any stngle control s} stem the boundary trehaves in a nombrtttle manner lag W &aem W the strvetural rod leak. nponent or channel, ce fauure of removal and (2) the probebtlity of rapidly propa. tight tategMty of lu coccponenta. (2) the 2m sortsce of any single protection aretem gattng fracture La minimMd The dealgTa operability and performance of the active caponent ce channel wh!ch La common to shall resect conalderation of servies tampers. cxnponents of the system, and (2) the oper. e control and protection systems leaves in. tures and other conditiona of the boundary aWHy of the system as a whole and, under
t a eystem satisfytng nu ret:abtuty, re. matertal under operst.tng, maintenance, test. candluona as close to design as pract:ctl. the andancy, and independence requirements tng and postulated accident conditions and P" # ***** # SD*IMU tbs protection system. Intercor.necuon of the uncertatntled La determining (1) mate. that brtage the s) stem'P*U***3 into Operation **9". "In.
- e protection and control erstems aban be rtal properties (2) the effects of trradlauon cluding opersuon of appucable portions of Alted no as to nasure that asisty is not alg. on material properties. (2) residual, steady. the prosecuco antent, the transfat between Scantly Impaired. state and transient stresses, and (4) staa of norma.1 and emergeccy power sources. and CHience 23-Protecitos splens requirs. 8A **- *** ** ** sts for reactivsty evnfroi etalfunctions. tember 1,1973 g p- - pe <cs pg U.S. ATOMIC ENERGY COMMISSION Ut u O ,,t,v m a i[. o g[ @ REGULATORY GUIDEDIRECTORATE OF REGULATORY STANDARDS REGut.ATORY GUIDE 1.45 REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION SYSTEMS A. INTRODUCTION L.sakage Separation General Design Criterion 30, " Quality of Reactor Coolant Pressure Boundary," of Appendix A to 10 A limited amount of leakage is expected from the RCPB and from auxiliary systems within the CFR Part 50, " General Design Criteria for Nuclear l Power Plants," requires that means be provided for containment such as from valve stem packing glands, l detecting and. to the extent practical, identifying the circulating pump shaft seals, and other equipment that Ivestion of the wurce of reactor coolant leakage. This cannot practically be made 100% leaktight. The reactor guide describes acceptable methods of implementing veuel closure seals and safety and relief valves should this requirement with regard to the selection ofleakage not leak significantly; however, if leakage occurs via detection systems for the reactor coolant these paths or via pump and vajve seals, it should be pessure boundary. This guide applies to light. water <ooled detectable and collectable and, to the extent practical, r ea c t ors. The Advisory Committee on Reactor isolated from the containment atmosphere so as not to Safeguards has been consulted concerning this guide mask any potentially serious im should it occur. and has cuncered in the regulatory position. These leakages are known as "ider *..fied leakage" and should be piped to tanks or sur.ips so that the now
8. DISCUSSION rate can be established and rnonitored durmg plant operation.
The safety signincance of leaks from the reactor coolant Uncollected leakage to the containment pessure boundary (RCPD) can vary widely depending on the source of the leak as well as the atmosphere from sources such as valve stem packing leakage rate and duration. Therefore, the detection and glands and other sources that increases the humidity of the containment. are not co!!ected monitoring of leakage of reactor coolant into the The containment area is necessary. In most cases, methods moisture removed from the atmosphere by air coolers for separating the leakage from an identined source together with any anociated liquid leakage to the from the leakage from an unidentiSed source are containment is known as " unidentified leakage" and necessary to provide prompt and quantitative should be cot!ccted in tanks or sumps where the Dow information to the operators to permit them to take rate can be establishs/ and monitored during plant immediate operation. A small anfount of unidentified leakage may corrective action should a leak be detrimental to the safety of the facility. Identined be impractical to e!!minate, but it should be reduced } leakage is: to a small now rate, preferably less than one gallon per (1) leakage into closed systems, such as pump seal or valve packing leaks that are captured, minute (gpm), to permit the leakage detection systems to detect positivel t and rapidly a smallincrease in now Gow metered, and conducted to a sump or collecting tank, or (2) leakage into the containment atmosphere rate. Thus a sind unidentified leakage rate that is of frtm sourecs that are both specincally located and concern will not be masked by a larger acceptable identified leakage rate. known either not to interfere with the operation of unidentified leakage monitoring systems or not to be fr:m a D w in the RCPB Unidentified leakage is ut! SubstanGal intersystem leakage from the RCPB to ether leakage. other systems across passive barriers or valves is not expected. However, should such leakage occur, it may UaAE C MEouLAToRY oUloE: c.pn se w6a ewe p.m , e. ee w a.w iery T.,.o e, w 6.s g e e.eennes W a.ees.=we ws.=mim ' sty.,,s.!.7,v
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. ~ . . . , .. ~w O". 1. h. "c. "..t.Me". . ",7:':;lr"""'"*",0,':;",:."2"T4. .e. a. . .6 64. ft.el uf f Sw %.f. 8.henen ea . ~. ~ ,f.s.t (fhe ,. - vlu. g 8 apt e G en t % .ma bread det.e Or e.a .aw.m . - .0.,f - of a persa er M 99 ffe - *mr I I =. o e CT::" .**:.:: ' r ~. ::::".=*TP;.'.::""'"" """~"*" i L'.":'::~~.'" .,0 Pa., .me  ! & .'.'".l::" m be detectable thruu;;h the above. mentioned specific nucle.1 power plant. However, since the c, lection systems .nd other alarm and detection methods differ in sensitivity and response time, prudent fet ethods should be ernployed. For example, steam selection of detection methods should include sufficient h. M ! fnerator leakage in pressunzed wat:r reactors (PWR's) systems to assure effective monitoring durmg penods 50uld be monitoreo to detect tube or tube sheet leaks. when some detection systems may be ineffective or inoperable. Some of these systems should serve as early sceptable Detection Methods alarm systems signaling the operators that closer examination of other detection systems is necessary to  ! ' Although monitoring of both identified and determine the extent of any corrective action that may vdentified leakage is important, effective systems for be required. tectmg and locating unidentified leakage are also Detector Sensitivity The following paragraphs describe some keded. eptable detection methods. It is essential that leakage detection systems have in addition to monito ing flow rate changes to tanks the capability to detect significant RCPB degradation as d sumps for liquid collection, other methods should soon after occurrence as practical to minimiae the Potentia! for s gross boundary failure. it is possible that feased included to indicate to the containment whenForand atmosphere. where some example, coolant cracks is might develop and penetrate the RCPB wall. 1 se cddition.d detecuon methods would indicate exhibit very slow growth, and afford ample time for a l Wur momtur changes m: safe and orderly plant shutdown after a leak ts detected.
a. airborne particulate radioactivity, On the other hand, leakage such as that resulting from
b. airborne gaseous radioactivity, stress. assisted corrosion in stainless steel or from a flaw
c. containment atmosphere humidity, at a high fatigue point in the RCPB would demand rapid
d. containment atmosphere pressure and detection and probable plant shutdown. Therefore, an ,
sperature, early warning signal is necessary to permit proper  !  ?
e. condensate flow rate from air coolers. evaluation of all urudentined leakage.
Since intersystem leakage does not release reactor Industry practice has shown that water flow rate I slant to the contamment atmosphere, detection changes of from 0.5 to 1.0 gpm can readily be detected ethods should include monitoring of water in containment sumps by monitoring changes in sump bioactivity in the connected systems where the water level,in flow rate,or in the operating frequency of items flows through the containment boundary, and Pumps. Sumps and tanks used to couect unidenufied , I onitoring c,f airborne radioactivity where such systems leakage and air cooler condensate should be instrumented to alarm for increases of from 0.5 to 1.0 I e vented outside the containment boundary. Another sportant method of obtaining indications of 8Pm in the normal flow rates. This sensitivity would icontrolled or undesirable intersystem flow would be Provide an acceptable performance for detecting e use of a water inventory balance designed to provide increases in unidentified liquid leakage by this rnethod. 3ropriate information such as abnormal water levels in aks and abnormal water flow rates. An increase in humidity of the containtnent atmosphere would indicate release of water vapor to the Potential discharges from closed safety and relief containment. Dew point temperature measurements can Ives are usuaDy piped to tanks or water pools and be used to menitor humidi*y levels of the containment nsidered part of identified leakage. Temperature atmosphere. A 1, increase in dew point is well within uors in the discharge path of safety and relief valves the sen.ativity range capability of available instruments, fisw meters in the leak.off lines would provide an Since the humidity level is influenced by several factors, ceptable method of sagnaling sm.ett leakage from these . a quantitative evaluation of an indicated Isakage rate Ives, may be questionable and should be compared to observed increases in liquid flow from sumps and While the above.mentior,ed leakage detection condensate flow from air coolers. Humidity level stems reflect the present state of technology, it is monitoring la considered most useful as an alarm or agnized that other detection methods may be indirect indicating device to alert the operator to a veloped and used in order to obtain operating Potential problem. perience with them. Arnong such methods are sonic dicators and moisture sensitive tapes applied to RCPB Reactor coolant normally contains sources of mponent parts. Because of the potential importance radiation which, when released to the containment, can early leak detection in the prevention of accidents, be detected by the monitoring systems. However, niinued improvements in leakage detection and reactor coolant radioactivity should be low during initial reactor startup and for a few weeks thereafter u,nti!
ating techniques should be sought, activated corrosion products have been formed and
[ it b not necessary that all of the above. mentioned fission products become available from failed fuel skage detection methods or systems be employed in a elements; during this period, radioactivity morutoring iA5 2 mstruments may be of limited value in providing an Signal Correlation and Calibration early wartung of very small leais in the RCPB. Instrument sensitmt.es of 10' uCi/cc radioactivity fo' It is important to be able to associate a signal or air particulate monitorms and of 104 pCi/cc indication of a change in the normal operating
adioactmty for radiogas monitoring are practical for concations with a quantitative leakage flow rate. Except these leakage de tection systems. Radioactivity for 11ow rate or level change measurements from tanks, l morutoring systems should be indud.J for every plant sumps, or pumps, sagnals from other leakage detection (especially particulate actmty monitoring) because of systems'do not provide information readily convertible '
their sermtmty and rapid respoue to leaks from the to a common denominator. Approximate relationships RCPB. converting these signals to units of water flow should be formulated to assist the operator in interpreting signals. Since operating conditions may influence some of the Air temperature and pressure monitoring methods conversion procedures, the procedures should be revised may also be used to infer RCPB leakage to the during such periods.To assure the wntinued reliability containment. Containment temperature and pressure of the leakage detection systems, the ent:ipment should fluctuate slightly durmg plant operation,but a rise above cornply with Paragraph 4.10 of IEEE Std. 279 1971, the normally mdicated range of values may Indicate " Criteria for Protection Systems for Nuclear Power RCPB leakage into ne contamment. The accuracy and Geneistmg Stations,"' for tests and calibration.  ; relevance of tempera.ute and pressuse measurements is a Letion of contatnm..st free volume and detector Seismsc Qualification ocation. Alarn signan rom these instruments can be raluable in reccpunng red ar.d sizable energy _zeicases Since nuclear power plants may be operating at the Lo the contamnur.t. time an carthquake occurs and may contn ue to operate after earthquakes, it is prudent to requia the leakage While the concern about instrument sensitivity detection systems to (.inction under the same spplies to the lower range of service for which the conditions. If a seismic event comparable to a safe hstruments are selected, the upper instrument range shutdown earthquake (SSE) occurs, it would be limits should be established to prevent exceeding the important for the operator to assess the condition within saturation limits of instruments. thus making them the containment quickly. The proper functiorung of at useiess as indicators of cuntasnment conditions. least one leakage detection system would assist in evaluating the seriousness of the conoition within the containment in the event !c.tkage has developed in the Detector Response Time RCPB. The airborne particulue radioactivity morutorms equipment has the desirab!s ansitivity to mdicate RCPB The need to evaluate the severity of an alarm or leakage, and it should be included for all p' ants. i dication is important to the operators, and the abJity Components for the airborne particulate radioactmty o compare with indications from other systems is 89uiPment should be qualined to function through the SSE. gecessary. The system response time should therefore be ncluded in the functional requirements for leakage biection systems. Except for the limitations during the C. REGULATORY POSITION }rutial few weeks of plant operation as discussed previously, all detector systems should respond to a one The source of reacto. solant le.;Lue should oc spm, or its equivalent, leakage increase in one hour or identifiable to the extent practical. A ator coolant less. Multiple instrument locations in monitored areas Pressure boundary leakage detecti:r. and coUection 6hould be utilised if necessary to assure that the systems should be selected and designed to include ne transport delay time of the leakage effluent from its IOU 0*in8: tource to the detector or instrument location will yield i in acceptable overall response time. A useful technique 1. tenkage to the primary reactor contamment from in identifying the generallocation of a leakage area is the identined sources should be collected or otherwne placing of several sensors within the containment area isolated so that: ind observing differences in response from the sensors, s. the flow rates are monitored separately from ind this technique should be used to satisfy this unidentiGed leakage, and
equirement of General Deugn Criterion 30. b. the wtal Nw sate can be e WiM and monitored.
In analyzing the sensitivity of leak detection systems using airborne particulate or gaseous 2. 1.eakage to the primary reactor containment fr en radioactivity, a realistic primary coolant radic :mty unidentined sources should be collected and the U
  • j concentrahon auumption should be used.The expectud ' cop,es may be ouained from the f amiuie of Dutrist values used in the plant environmental report would be r.nd Doctronics Engansers. United Enguwenns center, N5 tiu acceptable. 47th Street. New York, N.Y.10017.
e ne n .. J = s' rate monitored with an accuracy of one gallon per employed for unidentified leakage should be ndequate to $i minute (spm) or hetter. detect a leakage rate, or its equivalent, of one gpm m iess i than one hour.
3. At least three separate detection methods should be employed and two of these methods should be (1) su'mp 6. The leakage detection systems should be capable of level and flow monitoring and (2) airborne particulate performing their functions following seismic events that radioactivity monitoring. The third method may be do not require plant ahutdown.The airborne particulate selected from the following: radioactivity monitoring system should remam
a. monitoring of condensate flow rate from air functional when subjected to the SSE.
coolers,
b. monitoring or airborne gaseous radioactivity. 7. Indicators and alarrns for each leakage detection i Humidity, temperature, or pressure monitoring of system should be provided in the main control room. i the containment atmosphere should be considered as Procedures for converting various indications to a alarms or indirect indication of leakage to the common leakap equivalent should be available to the containment. Operators. De calibration of the indicators should account for noeded independent variables.
4 Previsions should be made to monitor systems l connected to the RCPB for signs ofintersystem leakage. 8. The leakage detection systems should be equipped Metheds should include radioaesivity monitoring and with provisions to tr.adily permit testing for operability indicators to show abnormal water levels or flow in the and calibration during plant operation. affected area. I
9. The technical specifications should include the limiting conditions for identified and unidentified
5. The sensitivity and response time of each leakage leakage and. address the availability of various types of detection system in regulatory position 3. above is.struments to assure adequate coverage at all times. I l
I s 1 I 1.45 4 ( 1 3 . l i 1 U.S. NUCLEAR REGULATORY COMMISSION Revision 4 i August 1975  ! REGULATORYGUIDE l OFFICE OF STANDARDS DEVELOPMENT l REGULATORY GUIDE 1.16 R ' EPORTING OF OPERATING INFORMATION-APPENDIX A TECHNICAL SPECIFICATIONS 1 1 [4 A. INTRODUCTION of Reporting Requirements for Pers s Subj . to NRC Section 50 36, " Technical Specifications." of 10 Regulations," and is not presentYd here CFR Part 50. " Licensing of Production and Utilization gTY { Facilities," requires that each app!icant for a license B. OfSC SSloy '.h.  ! ' authonzmg operation of a nudear power plant include , y in its application proposed technical specifications. in September)974 .. tomic Energy Commis-These technical specifications, as issued by the NRC. are sions Regulatory'staffpubt ed Revision 2 of Reguls. tory Guide.. T6> incorporated into the facility license and are conditions 3 of the beense. Technical specifications are now included review :of (operaThis rehsion renected results of me ten [ information needed to permit i as two appendices to the license: Appendix A technical assessineikby th'e Commission of safety.related activities specifications relate to health and safety, and Appendix during )hehera, ting phase of plant life. Significant iha Rension 2 were:  ; B technical specifications relate% pact.' Each of these appendices indudes a section oo to environmental imk porting requirements were updated to refleet hange,s in reports required by Appendix A technical reporting requirements. The reporting propam describe'd "' cifications. In general, these changes involved; in this segulatory guide involves the reporting raguire a. a change in frequency of submittal of ments cf Appendtx A technical specification'ong. Irr some cases, this program may need to be supp mente'd outine operating reports;  ; b. or modified because of unique plant design fe uy r report, elimination of the first year operatmg other factors. The need for a supplemental or modi ed I c. picgram wtl be determined on a case.by. case basis. forrnabration of reporting of operating Reporting of information lc1 cerning radioactive information on a monthly frequency; 9 d. discharges, radiolopeal envirocmep.tal monitoring, and deletion of certain items ofinformation no nonradiologi:al environment! sursed!ance and environ- longer required to be submitted on a routine basis; e. rnental impact is dispussehn Ngulatory Guide 4.8 changes in the format and immedia:y of " Environmental Tea ' cal Specincations for Nudear reporting required for certain types of abnorma! occur Power P! ants." \. ' rences (now called reportabh occurrences); and
f. improved guidance conceming definitions in additio ope'repo ang requirements necessary for comphance h technical specifications, specific re- and categories of significance of abnormal occurrences.
2. Ap'pendices were added to provide tne desired porting requireme'n are included in Part 50, as well as in other Parts of itle 10, Chapter I, Code of Federal format for radiation exposure reports and rncnthly operating reoorts Regulations. A compilation of all reporting requirements 3.
appbcable to the varicus types of NRC licensees,includ- A listmg of reports other than those re:pired siig identification 'of the propeFNRC addressee or ad by Appendix A techttical specifiestions was eliminated. diessees and designation of the numbeTorcopies reqbit. (See introduction above.) ed. is included in Regulatory Guide 10.1, " Compilation 2 I i 'A rew n, Atomic Energy Comr.i33;on me abotahed by the Ener;y I facihties have a angle appenda that contains the Reorgna:ation Act of 1974. whsch also created the Nudes.r comtuned aspect of Appendaces A and B Regubtory Commimon and gave it the beensmg ud rebted regutatory functions of the AEC. USNRC REGUL ATOR Y GUIDE S c.--.ai c....~ ,c .a*.as .. as v. m  ; ';;r c;--~ "- . swnn ,ec == n. c.... .. u a n.s.w c.-...........,..e....,.,................,... .,.....m.......................e.. . . . m. e'.' a a"~ oa*" ~ ..~.......,.c................................ e..... ........ . ~ . . .... ,,,,..,,,,,,...,-,..,,.,,,,,,,,,,....., ... ... e .. .. m . . ... . . ... . .. .. . ..-. .... ....~..............- ,......,,,,,,,,,,, ..............c.--...... ,,,,,,,,....,..... c,- *.4.*.,.... ........ ..... . .......... ...... m.q o....... s ~ ~..... ~ ...~ ...., ~ ... ,....,,,,,.....e
9. . e d8 . . . . .' . . . . .
4 4 , , t .bg . t .e e .* fJ..R es ,q g. ,d .. (. c . .. .. . 4 .*.4
  • c 4.'*. M ' . . I' #"'d . .*. . 84. . f . . . .a ..m . t,
...........e..........,...'1F**..e,,-......,8..e.... ...,,o . =* 4 8 ..*i.,.* ..........-......%.....,....o-...g...I**.d.fa81f9 ..-...-t.- r Comments were invited within 60 days of publica. I. Routine Reports ' l tion of Revision 2 for use in conjunction with early l revis:on of the guide. As a result of comments received s. Startup Report. on l developed Revision 3. Signincant changes in Revision 3the guide and additions! staff review, the staff were: A summary report of plant startup and power
1. The startup report was revised to be more escalation testing should be submitted fouowing (1) ,
receipt of an operating license, (2) amendment to the speciSc as to the test results to be reported.
2. License involving a planned increase in power level,(3)
The annual report section was revised to (1) installation of fuel that has a different design or has been further quantify the term " reduction in power," (2) provide further guidance on reporting of occupational manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the radiation exposures, and (3) revise the information to be . submitted on fuel performance. rauclear, thermal, or hydraulic performance of the plant.
3. The report should address each of the testsidentified in
{ The abnormal occurrence report section was the FSAR and should in generalinclude a description of revised to (1) provide for prompt notification by the measured values of the operating condinons or telephone and confirmation of such notification by characteristics cbtained during the test program and a telegraph, mailgram, or facsimile transmission of the comparison of these values with design predictions and types of abnormal occurrences listed under Section 2.a. (2) be more specific on the types of abnorma! occur. specifications. Any corrective actions that were required to obta:n satisfactory operation should also be de. rences reported. (3) delete radio!cgical ef0uent releases scribed. Additiona! specine details may be included m from Appendix A technical specification reporting bcense conditions based on the applicant's comnutment requirements, (4) provide for reporting of the types of to applicable regulatory guides and should be included in abnormal occurrences hsted under Section 2.b within 30 this report. days of occurrence of the event, and (5) make Section Startup reports should be submitted within (l) 2.c of Revision 2 of the guide a separate section (Section 4). 90 days foDowing completion of the startup test program, (2) 90 days foUowing resumption or com-l In previous revisions of Regulatory Guide 1.16, the mencement of commercial power operation, or (3) 9 iterm " abnormal occurrence" was uxd to designate any snonths fouowing initial criticality, whichever is earliest. l unscheduled or unanticipated operational event reported if the Startup Report does not cover all three events .to the Commisnon. Included in these reported events (i.e., irtitial criticality, completion of startup test pro. Sete (1) events that could or did have s:gni5can:e from gram, and resumpuon or commencement of commer:ial the standpoint of public health or safety and (2) events power operation), supplements y reports should be reported to NRC for performan;e evaluation and trend submitted at least every three months unti! au three determestions. In Section 205 of the Energy Reorgani. events have been completed. sation Act of 1974 (Pub. L 93-433). an " abnormal occunence"is defined for the purposes of the reporting b. Annual Operating Report.' requirements of the Act as an unscheduled inciden: or 9 vent which the Commission determines is signincant Routine operating reports covering the opera. from the standpotnt of pubbe health or safety. In order tion of the urut during the previous calendar year shou!J So be consistent with this definition, the events desig. be submitted prior to March 1 of each year. The inical nated in prenous resisions of this guide as " abnormal report should be submitted prior to Mar:h I of the year occurrences" are designated " reportable occunences" following initial criti;a!ity; in Revision 4. Any " reportable occunences" that are The primary purpose of ann ual opera ting reports determined by the Commission to be significant frc>m the is to permit annual evaluation by the NRC staff of operat. standpoint of pubbe health or safety will be further ing and maintenance experience throughout the nu: lear fes:gnated " abnormal occunences." power industry. The annual operating reports rnade by bcensees should provide a comprehensne summary of C. REGULATORY POSITION # ' '"" " I #' though some repetition of previously reporteJ mforma. In addaion to the app!2 Ale reporting requirements " "'Y # * * ""C" *" N'W >f Title 10, Code of Federal Regulations, the followmg Mpp to panously submitted reports should be clear >rogram for reporting of operating mformation provides Each annual operstmg report should in:lude. a acceptable basis to the NRC staff for meetmg the (1) A narrative summary of operstmg expen. ?portmg requirements of Appenda A technical specifi. ence during the report penod relating to safe operanan ations Reports submitted m accordance with this guide of the fact!ity, including safety.related maintenance not hould be addressed to the Dnector of the appropnate covered in item 1.b.(2)(c) below. {RC Rgonal Office unles, otherwise noted. 3 A un;te ,ubmatat may be made for a rnade und aan ' h taf'es mJwate substAntae chJ%es tro n previous issue. submntal should combme tho,e sA uo.% that att sow ~ 'O all unas at tre station. (2) For each outage or forced reduction in power' of over 20 percent of design power level where tests, ultrasonic tests, or visual examinations completed during the report period. the reduction extends for more than four hours: * (a) the proximate cause and the system and major component involved (if the outage or forced c. Monthly Operating Report. reduction in power involved equipment malfunction), (b) a bnef discussion of or reference to Routine reports of operating statistics and reports of) any reportable occurrences p(ertaining toexpenence the shutdown should be submitted on a monthly outage or power reduction; basis. The report formats set forth in Appen6ces B, C, (c) corrective action taken to reduce the and D to this guide should be completed in accordance probability of recurrence,if appropriate; with the instructions provided. The completed forms (d) operating time lost as a result of the should be submitted by the tenth of the month outage or power reduction (for scheduled or forced cut- following the calendar month covered by the report to a ges,5 use the generator offline hours; for forced re- the Director, Office of Management Information and ductions in power, use the approximate duration of op- Program Control, U.S. Nuclear Regulatory Commission eration at reduced power); Washington, D.C. 20555, with a copy to the appropnate (e) a desenption of major safety related NRC Regional Office. correctne maintenance performed during the outage or power reduction, inclu6ng the system and component 1 Reportable Occurrences involved and identification of the critical path activity . &ctating the length of the ou: age or power reduction; Guidance concerning reportable occurrences that and should be reported in different time frarnes is provided (f) a report of any sing'e release of radio- below. Supplements! reports may be required to fuUy activity or single radiation exposure specificaUy assoct-leted with the outage wruch accounts describe for ftnalmore than resolution of the10 e crected or supplements] reports, a licensee event occurrence. In cases of percent of the aDowable annual va]ues. rep rt should be completed and reference should be (3) A tabulation on an annual basis of the made to the original report date. number of station, utility, and ether personnel (in. cluding contractors) receiving exposures greater than a. 100 mrem /yr and their associated man. rem exposure Prompt Notification With Written Fouowup. accor6ng to work and job functions,' e g , reactor The types of events listed below shouU be operations and suncillince, insemce inspection, routine maintenance, special maintenance (describe ma:n te, reported as expeditiously as possible, but within 24 hours by telephone and confirmed by telegraph, mail. nance), waste processing and refueling. The dose assign. 8I2m, or facsimile transfusion to the Dtrector of the ments to vanous duty functions m.iy be estimates based on pocket dosimeter, TLD, or ftim badge measurements. appropnate NRC Regional OfSce, or his desipee, no ' Smau exposures total'ing less than 20 percent of the later than the first working day fouowing the event, with , indnidaal total dose need not be accounted for. In the a wntten foUowup report within two weeks A copy of the confirmation and the written fouowup report shouM oggregate, at least 80 percent of the total whole body also be sent to the Director, Ofnee of Manager ent dose received from external sources should be assigned information and Program Control. USNRC. The untten to specific major work functions. See Appenda A to this guide for a standard format for providing this foUowvp report should include, as a minimum, a . information. completed copy of the licensee event report form (see Appen&x E to this guide) used for entenng data into the (4) In6 cations of failed fuel resulting from irra6ated fuel examinations, including eddy current NRC's computer based file of information coacerning licensee events. (Instructions for completing these bcensee event report forms' are issued indmdually to 'The term " forced reduction ,n po*er" as used in eus gmdeeach and licensee.) Information prosided on the beensee as normally deftrud in the electnc power md stry means the occur ence of a component fadure or other condinon that egent report form should be supplemented, as needei requees that the load on the umt be reduced for corrective by additional narratine matenal to provide ep.1p!ere action ur.med.ately or up to and includtng the very nes: explanation of the Circumstances surrounfy the event, seekend Note that touttne pres en trs e ana ttiterance' (1) Failure of the reactor protection syster or su rs edlance, and cal bratwn actrvines requ trtng po wer reductions are not covered by dus secton. other systems subject to litnitinE safety s} stem setting O to irutiste the required protective function by the ur.e a The term " forced outage" as used 6n the guide and as normally defined in the electric po*er industry means the occurrence of morutcred parameter reaches the setpoint specified as a component fadure or other condibon that requires that the the limiting safery system setting in the technical spect0-urut be remosed from service for correcuve noon unmediately cr up to and uiduding the very nent weekend i DN tatialatwn supplements the requennents of 120 407 of instruction Manual Lia see Dent R epo" Fde. Off;.T cf 10 Cf R Part 20 .Marugement infor awn 2.N P ogre Con:t t. U 5 bh Regulatory Comrwe. hepon. D C. 20555 - cations or failure to complete the required protective function. The foUowing are examples: 8 (4) Reactivity anomabes involving disagreement (a) Reactor pressure exceeds limiting with the predicted value of reactivity balance under safety. system setting value without automatic trip. steady 4 tate conditions during power operation greater (b) Inabdity to trip and insert sufficient than or equal to 1% ak/k; a calculated reactivity balance control rods to achieve the technical specification shut. indicating a shutdown margin less conservative than l down marg n. specified in the technica! specifications; short. term react. ivity increases that correspond to a reactor penod ofless * (c) Failure of the reactor protective system to complete the required protective action once initj. than 5 seconds or,if subcritical, an unplanned reactiuty sted, insertion criticality. unplanned of more than 0.55 ak/k;or occurrence of any l Note: Instrument drift discovered as a result of testing (5) Fauure or malfunction of one or inore com. Ponents which prevents or could prevent, by itself, the need not be reported under this item but may be report. able under items 2.a(5).2.a(6), or 2.b(1) below. fulfi!] ment of the functional requirements of system (s) used to cope with accidents analyzed in the SAR. The fouowing are examples: (2) Operation of the unit or affected systems (a) Clogged fuel line(s) resulting in fadure when any parameter or operation subject to a limiting to supply fuel to the emergency generators. condition for operation is less conservative than the least (b) Multiple instrument drift resulting in conservative aspect of the limiting condition for opera. loss of protective function. tion estabbshed in the techruca] specincations. The fol. lowing are examples: (c) HPCI failure to start or failure to con. tinue running once imtiated. (a) Shutdown not begun within the speci. (6) Personnel error or procedural inadequacy fled time when unidentified reactor coolant leakage ex. which prevents or could prevent, by itself, the fulfill. ceeds the technical specificacons limit. (b) Failure of a system other than the rnent of the functional requirernents of systems required to cope with aecidents analyzed in the SAR. The foDow. systems subject to limiting safety 4ystem settings (see ing are examples: ! 2.a(1) above) to actuate, or actuation of such a system at a monitored parameter value less conservative than (a) Failure to restore a safety system to operability foUowing test or maintenance. that bsted in the technical specifications for the system. (c) Operation with unacceptable contain. (b) Improper procedure lead:ng to in. s ment leak rate type B or C test results. correct valve lineup which resulted in closure of one ' manual valve in each of two redundant safety in;ection (d) System cooldown at a rate exceedmg the technical specifications limit, subsystems and would have prevented injection on deman d. Note. If specified action is taken when a systern is found to be opera:mg between the most consenative and the N te: For items 2.a(5) and 2.a(6) reduced redundancy least consenative aspects of a bmiting condition for that does not result in loss of system function need not operstion bsted in the technica] specifications, the be reported under this section but may be reportable lirruting conchtion for operation is not considered to under items 2.b(2) and 2.b(3) below. have been violated and need not be reported under this item, but it may be reportable under item 2.b(2) below. (7) Conditions arising from natural or man-(3) Abnormal degradation discovered in fuel made events that, as a direct result of the esent, requee cladir'g. reactor coolant pressure boundary, or primary plant shutdown, operation of safety systems, or other containrnent. The fouowing are examples: protectise rneasures required by technical specifications. (a) Through wa!] fadure of piping or com' The following are examples: ponents of the reactor coolant pressure boundary. (a) Titreatened civil disturbances requiring (b) Steam generator tube thinning in excess ' plant shutdowm. of acceptance lirnits in Regula tory Guide 1.83, (b) Damage to the facility caused by fire, Insenice Inspection of Pressunzed Water Reacto' flood, earthquake, or other similar occurrences. Steam Generator Tubes , (8) Errors disconred in the trans:ent or (c) Weling or material defects greater than accident analpes or in the methods used for such those allowable by appbcable codes. analyses as described in the safety analysis report or in the bases for the technical specifications that have or Note: Leakage of valve packing or gaskets within the eu 2" per@d rnetor opushn 6 a rnmer less bmits for identified leakage set forth in technwat specifi. c nsenatise than assumed in the analyses.The fouowing cations need not be reported under this item. He examph (a) Loss of condenser vacuum resulting in samp6es are intendrJ to be nNetrate e only. reac:or pressure anJ Ilus transients thac peak at values hlfher th;n anal) t01 (b) Reactivity insertion delay times by reactor protection system longer than those used in the of the functional requirements of affected systems. The technical specification bases. following are examples: (9) Performance of structures, systems, or com. (a) One of the four scram dump volume ponents that requires remedial action or corrective level switches failed to operate during surveillance test. measures to prevent operation in a manner less conserva. (b) One of four reactor low. pressure tive than that assumed in the accident analyses in the switches operated at 885 psig instead of LSSS value of 900 psig. , safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically (c) Dunng test, one out of four under. voltage considered in the safety analysis repcrt or technical spe. reactor inp breaker. relays failed to perform its function of tnpping a cifications that require remedial action or corrective measures to prevent the existence or development of an (2) Conditions leading to operation in a de. unsafe condition. The following are examples: graded mode permitted by a limiting condition for operation, or plant shutdown required by a limiting (2) Axial flux ratios less conservative than condition for operation. The foUowing are examples: those for which conelations with overpower AT were based on core burnup projections. (a) Core spray pump breaker tripped after 20 minutes during test. Trip unit was found to be (b) Failure of a safety injection pump to defective, declared inoperable, and repaired. deliver the Dow rates assumed in the FSAR, (c) Degradation of hydrauuc shock sup. (b) Safety injection pump failed to start pressors to the extent that they could not perform their following system initiation. Required sunciUance on required safety function. redundant components was successfuUy completed. (d) Fadure of magnetic trip mechanisms (c) One of the two centrifugal charging on a safety.related circuit bract to provide trip on pumps became inoperable because of a faulty beanng. Redundant pump operabuity was conSrmed. ! instantaneous overcurrent as indicated on the manufac. ' turer's time current charactenstic curve. Note: Routine surveiUance testing, instrument calibra. (e) Failure of a safety / relief valve to close
after pressure has reduced below the required rescat tion, or preventive maintenance which require system
> valve. configurations as described in items 2.b(1) and 2.b(2) need not be reported except where test results them. (f) Thermal shock to the reactor coolant selves reveal a degraded mode as desenbed above system resulting from inadvertent safety injection actua. 150 0-Note: . . (3) Observed inadequacies in the implementa. This item is miended to provide for reporting of tion of adininistrative or procedural controls wtuch potentially genene problems threaten to cause reduction of degree of redundancy prov ded in reactor protection systems or engineered
b. Thirty. Day Written Reports. safety feature systerns. The followmg are examples:
(a) One of the three diesel Eenerators The reportable occurrences d:scussed below tripped from high temperature because cooling water should be the subject of wntten reports to the Director valves were imed up incorreedy. of the appropnate NRC Regional Office within 30 days (b) Isolation valve for a low. pressure trip if occunence of the event. A copy of the wntten report switch was found closed with system pressure locked in. $)ould also be sent to the Director, Office of Man 2Ee-Tnp of switch would not occur at low pressure. raent Impre, er retum to operation foUowing maintenance was Information and Program Control. The written the cause. eport should melude, as a mirumum, a completed copy >f the licensee event report form (see Appendtx E to (c) FaDure to perform surveillance tests at his guide) used for entering data into the NRC's the required frequency. omputer. based file of information concerning licensee vents. (Instruccons for completing these Lcensee event (4) Abnormal degradation of systems other ? port forms' are issued indwiduaUy to each beensee ) than those specined in item 2.a(3) above desiped to sformation provided on the licensee event report form contain radioactive rn.iterial resulting from the fisaon process sould be supplemented, as needed, by additional nura- For example, a through. wall leak in a liqud ve maten21 to provide complete explanacon of the cir, waste storage tank _ smstances sunounding the event. Note: (1) Reactor protection system or engineered Scaled sources or calibration sources are not ifety feature instrument settmgs utuch are found to be included under this item. Leakage of valve packing or as con >ervative than those estabhshed by the technical gaskets within the limits for identined leakage set forth 'eeMatmns but which do not prevent the fulfdiment in technical specifications need not be reported under this item, t 1.' s
3. Urdque Reporting Requirements c. Unscheduled shutdowns expected to last for more than one week, regardless of cause.
The above reporting prograrn will 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 propam ments. may need to be supplemented or mo6fied because of g. Fulure of or darnage 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 propam wiu be deter. if the time for repairislikely to exceed the time a!! owed truned on a case by. case basis and so designated in by the techrucal specifications.
individual operating licenses.
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. Whde some of the events may not tion to applicants and licensees regarding the NRC staffs be reportable by regulation or defined in other parts of plans for utdizing this regulatory guide. this guide, the Director of the appropriate NRC Regional Except in those cases in which the applicant Office, or his desigree, should be informed of such proposes an acceptable alternative method, the reporting events by telephone as soon as possible after the event progam desenbed herein is being used by the NRC staff has been discovered. in order to standardize the reporting requirements secion of Appendix A technical specifications of au
a. An event that causes damage to property or operating licenses.
equipment when such damage affects the power pra. For licensees holdmg operating licenses without duction capability of the facility. Appenda B emironmental technical specifications, it
b. Radiation exposure to licensee personnel or may be necessary to include those reports identified in members of the pubbe in excess of applicable exposure Regulatory Guide 1.21, " Measuring, Evaluating, and limits set forth in 10 CFR Part 20. Reporting Radioactivity in Solid Wastes and Releases of
c. Natural or mar made conditions that rnay Radioactive Matenals in Liquid and Gaseous EfDuents require action whach need not be repurted under item from lj ht. g Water Cooled Nuclear Power Plants," and 2.a(7) above. Regulatory Guide 4.1,"Propams for Monitoring Radio- '
d. Discovery of sipdfican: radiological event off. ac:mty tn the Environs of Nudear Power Plants,"in the
site occu nng dunng transport of material for which the techrucal specifications under the unique repomng beeruee was either shipper or consignee. requirements section of the technical specifications.
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.x E ; m t r. 5 2[3,sEE;3 E mt m  : E - ,3 . .2 x. _2 ,= _= -2_m. _,2.o__ ~tNEE _stn ca._.[3=_= m m .:2_Extr.,*Epstt e _ym, _, 2,2,c _2 ,;_2tr, s :: .__m_ -. _. APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. UNIT . DATE COMPLETED BY TELEPHONE MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 17 3 18 3 19 4 20 l 5 . - - - 21 1 6 22 7 23 8 24 9 25 10 26 11 27 12 28 g 13 29 14 30 15 - 31 16 MSTRUCTIONS n thiswhole tarest form, list the average dady unit power level in MWe Net for each day in the reporting month. Compute to the megawatt. Tese figures will be used to plot a graph for eseh reporting month. Note that when maximum dependh:e capacity :s ed for the net electrical rating of the unit there may be occasions when the daily average power k el eweeds the X)7e hne (or the restncted power level bne). In su:h ca>es, the average daily unit power outpet > Leet should be o:noted to expbin the apparent anomaly. 1 M.- o ,". i , 'h .j , ' t, # I, .t s ., 3 1 . t. 1 APPENDlX C OPERATING DATA REPOR1*. lr t4 i ,+ \ " h DOOKET NO. UNIT
  • i
. i . DATE i i COMPLETED BY 3 TELEPHONE a i V , OPERATINdhiATUS . ~
1. FIEPORTING PERIOD GROSS HOURS IN REPORTING PZRICtD:
a , >
3. C'!AREN*L Y AUTHORIZED POWER LEVEL (VWt): M AX. DEPEND CA'ACITY (MWe Ned' l DESIGN LLECTRICAL RATING (MWeNet): '
l \ POWER LEVEL TO-f[t41CH . , RESTRICTED (IF AN Y) (MWtNet):, . .3 l l
4. RE ASONS FOR RESTAn* TION (IF ANY): l
] THIS MONTH YR TO D ATE CUMULATIVE  !
5. NUMBER OF HOURS REACTOR WA$ CRITIC AL ,, . ...... ..
l
6. R1 ACTOR RESERVE SHUTDOWN ' HOURS , .. , . . . . ~,
t ( )
7. > q'R5 CENER ATOR ON LINE , , . .. . , ,
8. UNIT RESERVE SHUTDOWN HOURS .,,. ... .. . . ..
9. GROSS THERM &L ENERGY GENER ATED (MWH) . . ,,,,,,
10 GROSS ELECTRICAL ENERGY GENER ATED (Mpm) . . .. _-- If GE ELECTRICAL ENERGY GEf4f1R ATEDfMWH) r .. .. . ... .b- $i e PA ACTOR SERVICE FACTOR .. . ..'. . . . . ._
13. RLA.CTOR AVAILABILITY F ACTOR , . .. . , ,, , , .
10. UNIT SERVICE F ACTOR , ....... ., , ..  ;
15. UNIT AV AILABILITY F ACTOR . .... . . . . . .. ..
16. UNIT CAPACITY F ACTOR (Using MDC) . ...... .. ..-
17. UNIT CAPACITY F ACTOR (Uning Design MWel . . . . . . . ... ...
18. UNIT ibRCEO OUTAGE RATE ,.......... .. .
19 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE, AND OteR ATION OF E ACH); 6 l 30 IF SHUT DOWN AT END D5 REPORT PERIOD ESTIMA7(D DATE OF 'JTARTUP:
31. UNITS IN TEST STjTUS (PRIOR TO COMMERCIAL OPERATACN). FORECAST ACHIEVED i ,
INITIAL CRITICALITY a INITI AL ELECTRICITY _ COMMERCI AL OPER ATION . --  % 9 _--__.-_-----___1--__-_-.__- - , _ , . - . . - _ __ _ _ _ _ . . _ . _ . . _ - . _ _ __ _ _ . - _ . INSTRUCTIONS FOR COMPLETING OPERATING DATA REPORT l This report should be fumished each month by as specific as possible within space limitations. Plants in licensees. The name and telephone number of the startup and power ascension test phase should be preparer should be provided in the designated spaces, identified here. I The instructions below are provided to assist licensees in ' reporting the data consistently. The number of the S. Show the total number of hours the reactor was instruction corresponds to the item number of the critical dunng the poss hours of the reporting period. ' report form.
l. Reporting Period. Designate the month for which
6. Reactor Reserve Shutdown Hours. The total number of hours during the Eross hours of reporting the data are presented. The Crom Houn are normally from 0001 of the first day through 2400 of the last day Period that the reactor was removed from service for of the calendar month,with appropriate adjustments for administrative or other reasons but was available for any month in which a change from standard to oper2tiom daylight taving time (or vice versa) is rr.ade. The ortly ltwo shorter reporting penods are (1) the one in which 7. Hours Generator On Line. Also called Service l the mitial electrical genention occurs and (2) the one in Hours. The total number of hours dunng the poss hours l which the reactor is shut down for decommissioning. In of the reporting period that the unit operated with
the former, the gross houn, expressed to the nearest breakers closed to the station bus. These hours, plus
' tenth of an hour, are those from the time of initial those bsted in Appendix D for the generator outage power generation to 2400 of the last day of the calendar hours, should equal the poss hours in the reportmg month. In the latter case, the poss hom, expressed to Penod. the nearest tenth of an hour,are those from 0001 of the cdendar month to the specine time of final shutdown. 8. Unit Reserve Shutdown Hours. The total number of hours dunng the poss hours of the reporting penod 2.The Authorized Power Level is the maximum that the unit was removed from service for economic or thermal power, expressed in megswatts. currently similar reasons but was available for operation. i authonzed by the Nuclear Regulatory Comminion.
9. Gross Thermal Energy Generated. The thermal i The net Maimum Dependable Capacity is the poss output of the nuclear steam supply system du-ing the 'j electncal output as measured at the output terminals of poss hours of the reporting period, expressed in the turbine. generator during the most restnetive seasonal megawatt hours.
conditions less the normal station service loads.
10. Gross Electrical Energv Generated. The electrical The net De>ign Electrical Rating is the nomina! net output of the unit measured 'at the output terminals of electrical output of the unit speciDed by the utihty and the turbine-generator during the poss hour, of the ,
used for the purpose of plant design. reporting period, expressed in megawatt hours. l
3. Note that ttus item is applicab:e only if restric.  !
11. Net Electrical Energy Generated. The gross elec. J tions on the power level are in effect. Short. term (less than one month) hmitations on power level need not be trical output of the unit measured at the output j terminals of the turbine generator minus the normal i presented in thss item, since one of the important purposes of the item is to determine if, and at what station senice loads during the poss hours of the j power level, a restncted power level line should be reporting period, expressed in megswatt hours. Negatise g quantities should not be used. If there is no net pos:tne j drawn on the chart of aserage daily reactor power.
value for the period, enter zero. Since this information is used to develop figures on capa;ity lost due to restnctions and because most users 1219. For units still in the startup and power of the "Operatmg F. ant Status Report" are primarily ascension test phase, items 1218 should not be ecm. interested in energy actus!!y fed to the distnbution puted. Instead, enter N/A in the current month column. system. it is requested that this Ogure be expressed m These seven factors should be computed starting at the MWe. Net in spite of the fact that the figure must be time the unit is declared to be in commercial operation. densed from MW or percent power. The cumulative figures in the second and third columns should be based on commercial operation as a startmg t Reasons for Restriction (if Any). If item 3 is date. However, uruts already in commercial operation, used. item 4 explains why. Bnef narrative is acceptable, for which cumulative figures hase been based on , Cre refer:nces as appropnate InJi; ate whethertive restric. Agures. different starting dates.need not recalculate the cum tier. ce selfimpwd or are regulatory requirements. Be p 12. Reactor Service Factor. Compu$e by dividing 18. Unit Forced Outage Rate. Compute by dividing ! hours reactor was entical (item 5) by the you hours m the total forced outage hours (from the table in the reporting period (itsm 1). Express as percent to the Appendix D) by the sum of hours generator on lirie nearest tenth of a percent. Durmg months when the unit (item 7) plus total forced outage hours (from the table is shut down for the entire penod 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 melude reserve . shutdown hours in the calculation. 19. Shutdowns Scheduled to Begin in Next 6 Months. Include type (refueling, maintenance, other),
13. Reactor Availability Factor. Compute by divid- proposed date of start of shutdown, and proposed length ling the reactor available hours (items 5 plus 6) by the of shutdown. It is recognized that shutdowns may be gross hours in the reporting period (item 1). Express as scheduled between reports and that this item may not be i percent to the nearest tenth of a percent. all ine:.asive. Be as accurate as possible as of the date the report is prepared.
14. Unit Service Factor. Compute by dividmg hours the generator was on line (item 7) by the gross hours in 20. Self-explanatory.
the reporting penod (item 1). Express as percent to the l nearest tenth of a per
ent. Do not in:lude resene g g gg
shutdown hours in the calculation. mation is requested for aU uruts in startup and power ascension test status and is not required for units already m c mmerci peradon.
15. Unit Availability Factor. Compute by disidmg the urut available hours (item 7 plus item 8) by the you Test Status is defined as that period foUowing initial
hours m the reportmg period (item 1). Express as )
' percent to the nearest tenth of a percent. @y & N W s tested at messMy ' higher outputs, culminating with operation at full power for a sustained period and completion of warranty runs.
16. Ucit Capacity Factor (Using MDC). Compute by Followwg this phase, the unit is generaUy considered by dividing net eiectrical energy generated (item !!) by the the utibty to be avadable for commercial operation.
' product of maximum dependable capnity (item 2) l ' times the poss hours in the reportmg penod (item 1). Date of Commercial Operation is defined as the date ) ' Express as percent to the nearest tenth of a percent. that the unit was declared by the utility owner to be available for the regular production of electricity, i
17. Unit Capacity Factor (Using Design Electri::al usually related to the satisfactory completion of quabn- )
Rating) Compute as in item 16. substitutmg design cation tests as specified in the purchase contract and to ' eleetncal rating for ma.umum deper.dable capacity. the accounting policies and practices of the ut:hty i _ S T N E M ) M ) N O N I C IA A N L E E Y E / S P L ODN P X M T B N N X I T NO E A A DO O E ( CAI T ( N D E l i P I T E I R GA R O T T C R TNN R M I E E A U S E I I NMER) N A) N N L L E L I T I R A AVE I MR U P E V AS A C IA FE Y R XIT LA MT I T T T R T E A A PL O R ER N X R SL C CPX O C f R G I ST _ C E R P E M O.L N I T O NS STO A T LI IT(E LLA( AAMR E P TEL _ R O NI NUU ERI INARA C RE D UU OE ONNT11 O UI l G P LM:I ' I l' _ C S QAEL DP l I AAU1 I _ AEMRR O AOO TMMA0 E : :  : :  :
: I E : : : : .
_ RAI CDI E FGI M1 23 4 S N ) ) I O I ( 2 ( T C ) _ 2 U N R( _ D W OR E E R F O R OD OT W - l O . l DG C P E ON AG W HI E N T T O E T RI C P l M U E U D i T HHD N S T E N R A O S M N W T l ) 1 ( O l D o P N O T E S U t A I E H R S T I N N) U OS I T R AU O R U( H - D D E D L E U - EC PR D E YO H T F C F: S S E T A D _ O N i l l i UNIT SHUTDOWNS AND POWER REDUCTIONS @TRUCTIONS required to be trutiated by no later than the weekend following discovery of an off normal condition. It u This report should describe all plant shutdowns dur. recognized that some judgment ic reauired in categon. , 3 the report penod. In ad6 tion, it should be the zing shutdowns in this way, in general, a forced shut. down is one that would not have been completed in the 3rce of explanat2on of significant dips in average eer levelt (Appen6x B). Each significant reduction in absence of the con 6 tion for which corrective action was cer level (greater than 20% reduction in average daily taken. cer level for the preceding 24 hours) should be noted, ]n though the unit may not have been shut down Duration. Self explanatory. When a shutdown extends spletely.1 For such reductions in power level, the beyond the end of a report period, count only the time 3rstion should be listed as zero, the method of reduc. to the end of the report period and pick up the ensuing 9n should be listed as 4 (Other), and the Comments down tirne in the following report periods. Report durs. fumn should explain. The Comments column should tion of outages rounded to the nearest tenth of an hour used to provide any needed explanation not ade. to (s.:ilitate summation. The sum of the total outage 3ately desenbed by the coded columns. Please do not hours plus the hours the pnerator was on line (item 7 of 6 to the hst of codes or legends now fumished.Simi. Appen&x C) should equal the gross hoursin tne repon.
ly, do not add additional columns. tng period (iterr. I of Appendix C).
Reason. Categorize by letter desipation in accordance ember. This column should indicate the sequential with the table appearing en the report form. lf category vnber assigned to each shutdown or significant redue. H must be used, supply bnercomments. m in power for that calendar year. When a shutdown significant power reduction begins in one report Method of Shutting Down the Reactor or Reducing dod and ends in another, an entry should be made for Power. Categorize by number desipation in accord 2nce 9th report penods to be sure all shutdowns or sipifi. with the table appearing on the report form. If category at power reductions are reported. Until a unit has 4 rnust be used, supply brief cornments. , Meved its first power generation,no number should be 9 ped to each entry. Corrective Actions / Comments. Use this column to am. plify or explain the reasons for each shutdown or sipifi. cant power reduction, with the corrective action taken. ste. T!us column should indicate the date of the start 'esch thutdown or sipificant power reduction. Report if appropriate. The Cor".ments column entries should year, month, and day. August 14,1975 would be pronde identification of each shutdown or sipificant ported as 750814. When a shutdown or significant power reduction that occurs as a direct result of a re-swer reduction begins in one report penod and ends in portable occurrence on which a report has been or ws!! tother, an entry should be made for both report be submitted. (This information may not be immediately eriods to be sure all shutdowns or sigrtificant power evident for all such shutdowns, of course, since further ductions are reported. investigation may be required to ascertain whether or not a reportable occurrence was involved.) When a direet correlation can be made between a given shutdown and a
rpe. Ute "F" or "S" to in6cate either " Forced" or Beheduledl* respectively, for each shutdown or signifi. specific reportable occurrence report, the Comments at power reduction. Forced shutdowns include those column entry should state the reportable occurrence report number and date.
80te that trus ddfers from the Edison Electne institute (EEI) Summary. write a bney sumtrury descn.p !!on (3 ta *. Definitions of " Forced Pamal Outage" and "Schedded PanW sentences) of the highlights of operation of the unit for htagt" For these terms. EE! uses a change of 30 MW as the the reportir.g month. In.;lude any comments requ: red by pred point For larger power reactors, 30 Mw ss too small a Gar.ge to warrant captanation. item 12 of Appenix C. i i I APPENDIX E LICENSEE EVENT REPORT CONTROLGLOCK l l l I I l l LIC E NS E E ' EVENT LIC E NS E NAME LICENSE NUMBE R TYPE TYPE , hl l l l l l l l l l~l l l l l l~l l l l l l l l l i I 9 14. 15 25 26 ' 30 31 32 REPORTiREPORT t'.ATEGORY TYPE ASOURCE DOCKET NUMBER EVENT DATE REPORT DATE k0NT , Qse Q so l si l l l -l l j l l l l } l l l l l l l l l l l I ) 57 se es se 74 75 so EVENT DESCRIPTION l i 9 50 l I i 9 80 i 'l l 9 so )1 1 1 9 30 l f1 l ' 'S YSTE M CA USE hqy COMPONENT 80 CO ' COQE COMPONENT CODE SU ER M AN UF ACTU RE R VIOLATION [l. CODE I i LJ I' l I I I I I I I I lI l_J f9 10 11 12 17 43 44 47- og C AUSE DESCR9 TION ll l 9 30 'I l l 9 so i
l l 9 so P ACILITY METHCO08 STATUS  % POWER OTHER ST ATUS DISCOVERY OtSCOVERY DESCRIPTION
(_l 9 1 i t i i 10 . 12 j LJ i l 13 44 45 46 30 '[b NIN CONTENT AMOUNT OF ACTivtTy LOCATION OF RELE ASE REbE ASEO LJ OF l11 RELE ASE l I I  : 9 10 44 45 so  ! PERSONNEL E XPOSURES NUMSER TYPE DESCRIPTION I I I I LJ l I 9 11 12 13 30 PE RSONNE L INJURIES NUMBER DESCRIPTION l l l l l l 9 11 12 30 PRO 8ABLE CONSEQUENCES  ! l
  • so J LOSS OR OaMAGE TO 8 ACILITY 7YPE DESCRIPTION ~
L_l 1 l 0 10 go OUBLIC4TV I I O SO QOOITION AL F ACTORS i I O 80 , l l l 9 80 NAME. PHONE I l .. . I R 1 a T- 2EC lY _C SL/ ' ) . NUCLE / 2 STATiO1 UN T 2 TEC- 1 C/ _ PEClflC/ TIOM I TUCD BY THE UhlTED STATES NUCLEAR REGULATORY COMMITTION 1 DEFINITIONS CHANNEL FUNCTIONAL TEST , 1.11 A CHANNEL FUNCTIONAL TEST shall be: -
a. Analog channels - the injection of a simulated signal into the l channel as close to the primary sensor as practicable to verify - 1 OPERABILITY including alarm and/or trip functions. .
b. Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions. l CORE ALTERATION I I
1.12 CORE ALTERATION shall be the movement or manipulation of any com-ponent within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe conservative position. ) i SHUTDOWN MARGIN 1.13 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by 1 which the reactor is subcritical or would be subcritical from its I present condition assuming:
a. No change in axial power shaping rod position,
b. All control rod assemblies (safety and regulating) are fully inserted except for the single rod assembly of highest re- .
activity worth which is assumed to be fully withdrawn. 1 IDENTIFIED LEAKAGE 1.M IDENTIFIED LEAKAGE shall be:
a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured end ,
conducted to a sump er collecting tank,
b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.
THREE MILE ISLAND - UNIT 2 1-3 I I "DEFINITf0NS I
c. Reactor coolant system leakage through a steam generator to the secondary system. - )
q UN7DENTIFIED LEAKAGE 1.15 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE. PRES $URE BOUNDARY LEAKAGE 1.16 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator ' tube leakage) through a non-isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall. . J CONTROLLED LEAKAGE i 1.17 CONTROLLED LEAKAGE shall be that seal water flow supplied from the reactor coolant pump seals. QUADRANT POWER TILT 1.18 QUADRANT POWER TILT is defined by the following equation and is expressed in percent. QUADRANT POWER TILT = Power in any core cuadrant 100 ( Average power of all quadrants , )) DOSE EQUIVALENT I-131 1.19 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (uci/ gram) thich alone would produce the same thyroid dose as the quantity and l { 9sotopic mixture of I-131. I-132 I-133, I-134 and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be  % hose listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites." if - AVERAGE DISINTEGRATION ENERGY 1.20 T-AVERAGE DISINTEGRATION ENERGY shall be the average (weighted in j @roportion to the concentration of each radionuclides in the reactor coolant  ! st the time of sampling) of tne sum of the average beta and gamma energies l THREE M1LE ISLAND - UNIT 2 1-4 I I REACTOR COOLANT SYSTEM _ l l 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION i 3.4.6.1 The following Reactor Coolant System leakage detection systems .! 1 shall be OPERABLE: j
a. The containment atnesphere particulate radioactivity monitor- J ing system. l
]
b. The containment sump level monitoring system.
c. Either the containment air cooler condensate excess flow detection system or a containment atmosphere gaseous radio-activity monitoring system. ,
j APPLICABILITY _: MODES 1, 2, 3 and 4. ) ACTION: With only two of the above required leakage detection systems OPERABLE,  ! operation may continue for up to 30 days provided grab samples are obtained and analyzed at least once per 24 hours when the required gaseous and/or otherwise be particulate radioactivity monitoring system is inoperable; in at least HOT STANOBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS l 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by: i t l l THREE MILE ISLANO - UNIT 2 3/4 4-13 J ~ REACTOR COOLANT SYSTEM  ; SURVEILLANCE REQUIREMENTS (Continued) ) l a. Containment. atmosphere particulate monitoring system-performance l of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL
TEST at the frequencies specified in Table 4.3-3.
[ b. ! Containment sump level monitoring system-perforinance of CHANNEL )' CALIBRATION at least once per 18 months.
c. Containment atmosphere gaseous monitoring system-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3.
d. Containment air cooler condensate excess flow detection system-performance of CHANNEL CALIBRATION at least once per 18 months.
1 THREE MILE ISLAND - UNIT 2 3/4 4-14 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION ) 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a. No PRESSURE BOUNDARY LEAKAGE.
b. 1 GPM UNIDENTIFIED LEAKAGE.
c. 1 GPM total primary-to-secondary leakage through steam gen-erators. ,
d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System.
e. 8 GPM CONTROLLED LEAKAGE at a Reactor Coolant System i pressure of 2155 + 50 psig.
APPLICABILITY: MODES 1. 2, 3 and 4. , !- ACTION: l
a. Wit'h any PRESSURE BOUNDARY LEAKAGE, be in at.1 east HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30  :
l hours. ,
b. With any Reactor Coolant System leakage greater than any one '
of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
a. Monitoring the containment atmosphere particulate radioactivity monitor at least once per 12 hours.  !
b. Monitoring the containment sump inventory and discharge at least once per 12 hours.
l THREE MILE ISLAND - UNIT 2' 3/4 4-15 l _ ---mm -__ _ _ _ i RACTOR COOLANT SYSTEM _ h NRVEILLANCE REQUIRDiENTS (Continued) )
c. Measurement of the CONTROLLED LEAKAGE from the reactor coolant pump seals when the Reactor Coolant System pressure is 2155
+ 50 psig at least once per 31 days. l
d. Performe.nce of a Reactor Coolant System water inventory balance at least once per 72 hours during steady state operation.
i 9 e G .THREE MILE ISLAND - UNIT 2 3/4 4-16 l O 4 I REACTOR COOLANT SYSTEM l BASES I [ 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to detect and monitor leakage from the Reactor Coolant Pressure Boundary. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973. 3/4.4.6.2 OPERATIONAL LEAKAGE j PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN. Industry experience has shown that, while a limited amount of leakage is expected from the RCS, the UNIDENTIFIED LEAKAGE portion of this can be reduced to a threshold value of less than 1 GPM. This threshold value is sufficiently low to ensure early detection of additional leakage. The total steam generator tube leakage limit of 1 GPS for all steam generators ensures that the dosage contribution from tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break. The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents. The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a linited amount of leakage from known sources whose presence will not ine.erfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems. The CONTROLLED LEAKAGE limit of 8 GPMJestricts operation with a total RCS leakage to all RC pump seals in excess of 8 GPM. I 6 THREE MILE ISLAND - UNIT 2 B 3/4 4 2 l ADMINISTRATIVE CONTROLS i - - . . MEETING FREQUENCY l
6. 5.1.4 The PORC shall meet at least once per calendar month
  • and as convened by the Chairman or his designated alternate.
QUORUM 6.5.1.5 A quorum of the PORC shall consist of the Chatraan or his designated alternate and four members including alternates. l RESPONSIBILITIES 6.5.1.6 The Plant Operations Review Committee shall be responsible for:
a. Review of 1) all procedures required by Specification 6.8 and l changes thereto, 2) any other proposed procedures or changes l thereto as determined by the Unit Superintendent to affect nuclear safety.
b. Review of all proposed tests and experiments that affect nuclear safety,
c. Review of 511 proposed changes to Appendix "A" Technical Specifications,
d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety. i
e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Station Superintendent and the Generation Review Committee (GRC) Chairman,
f. Review of events requiring 24 hour notification to the Commission.
g. Review of unit operations to detect potential nuclear safety hazards.
h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Unit Superintendent and/or the Station Superintendent.
THREE MILE ISLAND - UNIT 2 6-5 l 3 pMINISTRATIVECONTROLS . 5 .1.6 RESPONSIBILITY (Continued) j
1. Review of the Security Plan and implementing procedures and shall submit recommended changes to the Unit Superintendent and the Station Superintendent.
j. Review of the Emergency Plan and implementing procedures and shall submit reconnended changes to the Unit Superintendent and the15tation Superintendent. ,
NTHORITY ) . 5.1.7 The Plant Operations Review Committee shall: l l
a. Recommend disapproval oftoitems the Unit Superintendent considered in writing),
under 6.5.1.6(a approval or through(d) above.
b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) ebove con-stitutes an unreviewed safety question.
c. Provide written notification within 24 hours to the Station Superintendent and the GRC Chairman of disagreement between ,
the PORC and the Unit Superintendent; however, the Unit ( Superintendent shall have responsibility for resolution of I such disagreements pursuant to 6.1.1 above. , DECORDS
3. 5.1. 8 The Plant Operations Review Comittee shall maintain written Iinutes of each meeting and copies shall be provided to the Station i superintendent and the GRC Chairman.
2.5.2 GENERATION REVIEW COMMITTEE (GRC) MNCTION
3. 5. 2.1 The Generation Review Comittee (GRC) shall function to provide '
Independent review and audit of designated activities in the areas of:
a. Nuclear unit operations
b. Nuclear engineering HREE MILE ISLAND - UNIT 2 6-6
ADMINISTRATIVE CONTROLS MONTHLY OPERATING rep 0RT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office, no later than the 15th of each month following the calendar month covered by the report. REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Speci fications 6.9.1.8 and 6.9.1.9, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to 4 the original report date. PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP
6. 9.1. 8 The types of events listed below shall be reported within 24 hours by telephone and confimed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate g 7
l no later than the first working day following the event, with a written i followup report within 14 days. The written followup report shall l include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report fom shall be supple- l mented, as needed, by additional narrative material to provide complete  ! explanation of the circumstances surrounding the event.
a. Failure of the reactor protection system or other systems f subject to limiting safety system settings to initiate the required protective function by the time a monitored para-mater reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.
b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation f is less conservative than the least conservative aspect of the limiting condition for operation established in the technical s peci fi catiens .
c. Abnomal degradation discovered in fuel cladding, reactor l coolant pressure boundary, or primary containment. l THREE MILE ISLAND - UNIT 2 6-15
i 1 ADMINISTRATIVE CONTROLS
d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% ak/k; a calculated reactivity balance indicating a SHUTDOWN MARGIN ,
less conservative than specified in the technical specifica-  ! tions; short-term reactivity increases that correspond to  ! a reactor period of less than 5 seconds or, if suberitical, I an unplanned reactivity insertion of more than 0.5% ak/k; or  ! occurrence of any unplanned criticality.
e. Failure or malfunction of one or more components which prevents-or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed i in the SAR.
f. Personnel error or procedural inadequacy which prevents or could  !
prevent, by itself, the fulfillment of the functional require-ments of systems required to cope with accidents analyzed in the SAR.
g. Conditions arising from natural or man-made events that, as a ,
direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by technical specifications.
h. Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
i. Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifica-tions bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or cor-rective measures to prevent the existence or development of an unsafe condition.
THfRTY DAY WRITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Ofrector of the Regional Office within thirty days of 1 THREE MILE ISLAND - UNIT 2 6-16. 1 l ADMINISTRATIVE CONTROLS occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report fom. Information provided on the licensee event report fonn shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
a. Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or unit shutdown re-quired by a limiting condition for operation. ,
i
c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
l l d. Abnormal degradation of systems other than those specified in 6.9.1.8.c above designed to contain radioactive material resulting from the fission process. SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activites identified below pursuant to the requirements of the ap-plicable reference specification:
a. ECCS Actuation, Specifications 3.5.2 and 3.5.3.
b. Inoperable Seismic Monitoring Instrumentation Specification 3.3.3.3.
c. Inoperable Meteorological Monitoring Instrumentation Specifi-cation 3.3.3.4.
d. Structural Integrity Test, Specification 4.6.1. 6.3.
e. Integrated Leak Rate Test, Specification 4.6.1.2.
f. Fire Detection Instrumentation Specification 3.3.3.8.
g. Fire Suppression Systems, Specification 3.7.10.1, 3.7.10.2, and 3.7.10.3.
THREE MILE ISLAND - UNIT 2 6-17 i l l 20MINISTRATIVE CONTROLS 0
3. 9 REPORTINGREQUIREMENTS(Continued) j
h. Seismic event analysis. Specification 4.3.3.3.2. l
1. Flood protection. Specification 4.7.6.1.3.
L10 RECORD RETENTION l 3.10.'1 The following records shall be retained for at least five years:
a. Records and logs of unit operation covering time interval .
at each power level,
b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c. ALL REPORTABLE OCCURRENCES submitted to the Conrnission.
d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e. Records of changes made to the procedures required by Specification 6.8.1.
f. Records of radioactive shipments.
f
g. Records of sealed source and fission detector leak tests and results. 4
h. Records of annual physical inventory of all sealed source  ;
material of re:ord. @.10.2 The following records shall be retained for the duration of the Pacility Operating License:
a. Records and drawing changes reflecting facility design modifi-  !
cations made to systems and equipment described in the 1 Safety Analysis Report.-
b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c. Records of unit radiation and contamination surveys.
d. Records of radiation exposure for all individuals entering radiation control areas.
g THREE MILE ISLAND - UNIT 2 6-18 4 j TABLE 1.1 OPERATIONAL MODES REACTIVITY 5 RATED AVERAGE COOLANT THERMAL POWER
  • TEMPERATURE MODE CON 0! TION, K,ff
1. POWER OPERATION 1 0.99 > 51 1 280*F j i
2. STARTUP g 0.99 1 5% t 280*F l
3. HOT STANDBY < 0.99 0 1 280*F 4 HOT SHUTOOWN < 0.99 0 280'F > T,yg > 200'F
5. COLD SHUTCOWN < 0.99 0 1 200'F
6. REFUELING" < 0.95 0 < 140*F Excluding decay heat.
Reactor vessel head unbolted or removed and fuel in the vessel. THREE MILE ISLAND - UNIT 2 17 - - - - - - - - - _-_________-_ _ _}}