Text

E-mail from D Millar to T Alexion Regarding Draft Amendment Request for ANO-2, Revising Section 6, and Various Supporting TS
	ML030370298
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/31/2002
From:	Millar D; Entergy Nuclear Operations
To:	Alexion T; NRC/NRR/DLPM/LPD4
	Alexion T W,NRR/DLPM,415-1326
Shared Package
ML030420086	List: ML030370171; ML030370172; ML030370238; ML030370243; ML030370253; ML030370275; ML030370298;
References
	Download: ML030370298 (104)
	v • d • e

December 31, 2002

Tom, Enclosed please find a draft copy of the proposed change to reorganize Section 6.0 of the ANO-2 Technical Specifications. I am still writing letter but want to talk with you and Bob before I complete the letter to be sure I am communicating the information in a way that will assist Bob in the review.

Thank you in advance for your assistance, Dana Millar Entergy

2CAN0103XX January 30, 2003 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Arkansas Nuclear One, Unit?-.

Docket No. 50-368 License Amendment Req ::&o Revisn4.jous Techic cifications and the Administrative ContrlU ***Te

REFERENCES:

1. Letter date osed Emergency Plan Change (OCANOBOI 0. '100

2. Letter dated F ja 2" '1QAddit"na!

Information Concerning

,op.. ed AdmirivT,*. i .... lical Specifications Changes

-*(*cAI*'d"'A.1..d 3:.d.YLetter .9902)Marcn.

-gi*>Ltt" :*t: ""Mr " , Issuance of Amendment No. 180 to Facility prating Lic.se No. NPF-6 -Arkansas Nuclear One, Unit 2 (TAQ4. M773995 TNA039701)

AI 'u.yi 2 I Change to the ANO-2 Reactor Coolant Q.-.sF t Inte.1 Interval Surveillance Requirements

V. *.., ( 1070107) ancd. *sequent NRC Safety Evaluation Related to

¢" ~ IPA0 "mendment 241, dated April 11, 2002 5 ' C t Evaluation Related to ANO-2 Amendment 218, dated

6. r date March 13, 2002, Proposed Changes to Support Ihementation of ANO-1 Improved Technical Specifications (ITS)

AN030201)

Tk and subsequent NRC Safety Evaluation Related to S N Amendment 218 dated June 10, 2002 (TAC NO. MB4750)

-1

\V7P*NRC Approval of Quality Assurance Program Manual dated November 6,1998 (TAC NO. M97893)

8. NRC Safety Evaluation Related to ANO-2 Amendment 180, dated March 7, 1997 (Addition of Low Temperature Overpressure Protection Requirements)

9. Letter dated January 31, 2002, Revision of Section 6.0, Administrative Controls For Consistency with ANO-1 Improved Technical Specifications (2CAN010203)

10. Letter dated June 26, 2002, Revision of Section 6.0, Administrative Controls For Consistency with ANO-1 Improved Technical Specifications (2CAN060203)

2CAN0103XX Page 2 of X

Dear Sir or Madam:

By letters (References 9 and 10), Entergy Operations, Inc. (Entergy) proposed changes to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TSs) to reorganize the Administrative Controls section of the ANO-2 TSs and to modify various other TS actions and surveillance requirements. Based on reviews by your staff, more detailed explanations and justifications were requested. In addition, it was encouraged ithe presentation of the proposed change be modified similar to the format used for imp

TS conversion projects.

Therefore, in order to accommodate these requests, this let l supercede the previously submitted requests (References 9 and 10). ..

Pursuant to 10CFR50.90, Entergy Operations, Inc. (.Etdery) her I1uests the following amendment for Arkansas Nuclear One, Unit 2 Q61 4d): 1) reorgaiion of the ANO-2 Technical Specification (TS) Section 6.0 Administ_4v Controls; and 2) mbation of various TS actions and surveillance requirements. OF"C The proposed change has been evaluated in ac e CFR50*91(a)(1) using criteria in 10CFR50.92(c) and it has been determined that t' t* 'hne '*e involves Invle no significant hazards considerations. The bases for these dct irnations are Wuded in the attached submittal.

The proposed change includes new co ;l.itsumm*Ned in Attachment 4. The NRC has not approved similar Technical SpecM tion f.r Jnqgot%,lants.

Entergy requests approy01014&"b oe Iet y*W19, 2003. Once approved, the amendment shall be Iientedjhin 120 Although this request is neither exigent nor emergency, your pop review is d.

If you have any ques opor re

hiona/ii ation, please contact Dana Millar at 601 368-5445 ,. i X.

I deciarmti-ndler perias-.jWf pe ~hat the foregoing is true and correct. Executed on January 30, U~

Sincerely, CGA/dm Attachments:

1. Analysis of Proposed Technical Specification Change

2. Proposed Technical Specification Changes (mark-up)

3. Changes to TS Bases pages - For Information Only

4. List of Regulatory Commitments

2CAN0103XX Page 3 of X cc: Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Thomas W. Alexion MS O-7D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Heal'M 4815 West Markham Street Little Rock, AR 72205 N

Change Attachment I to 2CAN0103XX Page 1 of X

1.0 DESCRIPTION

This letter is a request to amend Operating License NPF-6 for Arkansas Nuclear One, Unit 2 (ANO-2).

The proposed changes will revise the ANO-2 Technical Specifications as follows:

1.1 Facility Operating License (FOL) Changes FOL 2.C.(5), Secondary Water Chemistry Monitoring f This license condition will be deleted and an e(..al rogrammatic requirement will be added as proposed TS (PTS) 6.5.10.... quir e4 of the condition will be retained with only minor non-technical ae d istrative cha t, See Discussion of Changes (DOC) Al and A3.

ANO-1 Comparison The proposed change is consistent with ite... pecification 5.5. 10.

NUREG-1432 Comparison t],

NUREG-1432, Revision ,2%S pecifications Combustion NUREngine1tin32,a Reisio Engneein Pln*".,descrb *t, aefaf ' ;l . provides controls to inhibit EngineessrinePats dsrie'$ pr:ocra p* hs low pressure tuýbk lsc stress c well as Steam Generator (SG) tube degra'T .rrent A ý165#01-OL requirement does not include the words that the pgr1m inhibi w presibie turbine disc stress corrosion cracking. The propose, Qission of tording d to the stress corrosion cracking on the low pre ss ure (te evaluation o**; disoi conistent 4W.7the ei"*': approved wording in ANO-1 ITS. An evalatio 'NdKstry to maximize the turbine availability is

'i'r:'*: P fmiEd under a i8A rative controls (Procedure 1000.043) and it is A'op6ged, c n IN*-n

t.to be controlled in this manner. Therefore, the proposed S-"change t 'NO will differ from NUREG-1432 based on using the currently approved wor' cont1%d in the FOL.

L 2.C.(5), Pro ra to Reduce Leakage Outside Containment Thig nse c ion will be deleted and an equivalent programmatic requirement will be Xed'iPTS 6.5.2. The requirements of the condition will be retained with only min iiiechnical administrative changes. See DOC Al and A3.

ANO-1 Comparison The proposed change is consistent with the ANO-1 TS.

NUREG-1432 Comparison NUREG-1432, section 5.5.2 includes a listing of systems that are considered primary coolant sources outside containment. This list is not incorporated. The

Attachment I to 2CAN 0103XX Page 2 of X systems to which the program is applied have been previously identified in response to NUREG-0578. The application is adequately controlled through the design modification process and application of 10 CFR 50.59, "Changes,Tests, and Experiments." Therefore, the list of systems to which the program is applies will not be included in the proposed change and it is proposed to continue to administratively control the systems to which the specification is applicable.

FOL 2.C.(6), Program to Determine Airborne Iodine ntration in Vital Areas under Accident Conditions This license condition will be deleted and no *ve programmatic requirement will be added. See DOC A5.

ANO-I Comparison This license condition is still cont 1`1- in the AN1 ITS as tion 5.5.3.

NUREG-1430, Revision 2, "Babcock' hcl wii ants," does n' include an

,N .. G-14 32.

allowance to delete this requirement as *,, I.M NUREG-1432 Comparison-`:.........

NUREG-1432, specification .3i.a r's note that states: "This program may be eliminated o%"-ped

.... men14eion of Topical Report CE NPSD-1r157,machnical tf bn foi1!E*imination of the Post- Accident Sampling S*..{.e~ froiM* Plant W00in" and Licensing Basis for CEOG Utilities," and the assopit' fNRC Sat Evaluatio dated May 16, 2000."

ANO-2 hi{s i1iminate=&.h*.os~t, acci, sampling system requirements from TSs with the affi dated August 17, 2000 (reference 5).

ffiRle this" ftondition wii bdeleted and no new TS will be established as

tl*)web~ e re s note in NUREG-1432.

1.2 1adex Pages..

The tndex pages willib changed to reflect the correct titles and page numbers based on the a. nges propo*d. The proposed changes are non-technical administrative changr e DO'...

1.3 Section 1.0,'fintlons -Core Operating Limits Report, 1.33 The reference to Technical Specification 6.9.5 will be changed to Technical Specification 6.6.5. See DOC Al.

ANO-1 ITS and NUREG-1432 Comparison As this is a reference change only, no attempt is made to change the definition to be consistent with the ANO-1 ITS or NUREG-1432 definition. The currently approved wording will be maintained with only the change to the referenced TS.

1.4 Radiation Monitoring Instrumentation, TS 3.3.3.1, Table 3.3-6

Attachment I to 2CAN0103XX Page 3 of X A new action 21 will be added and annotated in the ACTION column for item 2.b, Control Room Ventilation Intake Duct Monitors In addition the page format will be changed from landscape to portrait. See DOC Al.

1.5 Radiation Monitoring Instrumentation, TS 3.3.3.1, Table 3.3-6 able Notation Action 17 Action 17 will be modified to be applicable in M * '.1 or 4 and a shutdown statement will be added. See DOC Al, M4, andy... sn tN Actions 18 and 19 2) will be changed to direc .'ISpecial Rep.,e See DOC A6.

ANO-1 ITS Comparison ANO-1 ITS 3.3.16 describes the Control ion - I Radiation function.

Actions Moe B,2 and3o C of the

.Te ANO-lsipecification rpjW."'- -ft*.i aA"'s.ihe Ts.* inoperability of two channels in Modes 1, 2, 3 or 4. The prop6 ange is con with the allowable outage times contained in the ANO-1 ITS. ~ I~ ,up to the f~t of ITS vice the format of the ANO-2 CTS, wording differences. noposed of change is the same as the ANO-1 ITS.

NUREG-1432 o0i *ans}v The followi oto REG-14 re noted:

fo~wneceptions tc nted NUREG-14520 9eqi$fEs erability of only one control room isolation 6i0;l\annel proposed *ine and the existing ANO-2 TSs require two icontrot M ,Ow o intake duct monitors to be operable. The two units share the SANO conti 0om ation system and isolation is provided by one channel i primarily, bu associated with each unit. The channel associated with

,each unit in' conolroom emergency ventilation system for that unit, but

%prvides isolatio ir both units' control rooms since they are a shared facility. Since t...,are two ch riels, appropriate ACTIONS are included. Conditions A & B of NU 1432 .

..-..- address the required actions when in Modes 1, 2, 3, or 4. The propo re ilar to NUREG-1432 with the same completion times.

NUREG-12 3.3.9 includes a note related to the toxic gas protection mode. The ANO control room emergency recirculation mode is the same as a toxic gas protection mode. Therefore, the note in NUREG LCO 3.3.9 Required Action A. 1 is not required.

to 2CAN0103XX Page 4 of X Action 20 Action 20 will be modified to be applicable in Modes 1, 2, 3, or 4 and a shutdown statement will be added. See DOC M3, M4, and M5 ANO-1 ITS Comparison ANO-1 ITS 3.3.16 Actions A and C are associated with the inoperability of one channel.

Action A allows 7 days to place one OPERABLE Control hb..

Emergency Ventilation System train in the emergency recirculation mode. Acti *quires the unit be in Mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Mode 5 in the following 30 hofgi£ne operable control room ventilation system cannot be placed in the emerger*$b idation mode of operation within the 7 day allowance of action A. The)pppFsd chprtoe is consistent with the allowable outage times. Due to ITS format a g rules, l rding in the ANO-2 proposed change is not exactly the same ANO-1 ITS. Ho intent of the ANO-1 specification is reflected in the prop. wording.

NUREG-1432 Comparison .

NUREG-1432 one LCO 3.3.9Becaiaddr*s*es the controlN operable channel. " .- OM isolation signal and requires only require c4.hannels to be operable, there is no related NUREG-1432 condi tr -.

Action 21 A new Action 1MI"be d which aapplicab l uring handling of irradiated fuel.

See DOC M i* '

ANO-1 ITS Cb arison Af:QZ*.*IfT: 3 3.1:c.. D addreN vIe necessary actions related to one or two an'Is

oi o fte* during movement of irradiated fuel. The proposed change is A:o.isistent wi": 1aci4,*Although the wording of the proposed change for ANO-2 is ot exactly the sat the ding contained in the ANO-1 ITS, the intent is the same.

NtJ'EG-1432 ComlDon NUREN .... LCQ.1- 9 addresses the control room isolation signal and requires only one opei Condition C addresses the required actions during movement of recently irrdIt uel assemblies. The proposed change is similar in that it requires immediate actions upon discovery of one or two inoperable channels.

Attachment I to 2CAN0103XX Page 5 of X 1.6 Radiation Monitoring Instrumentation Surveillance Requirements, Table 4.3-3 A new Note 6 will be added to item 2.b. The addition of the reference to Note 6 in the Channel Functional Test column and the change of the page format from landscape to portrait are administrative. See DOC Al. The addition of Note 6 is less restrictive. See DOC L2.

ANO-1 ITS Comparison The adoption of the note related to the channel functi est into the ANO-2 TS is consistent with the note contained in the ANO-1 ITS -R.316.2. However, the noun name of the control room ventilation intake duct ud in the ANO-2 TS r used which is consistent with the current noun name injth l0-2 The ANO-1 CTS contained a note stating " unctioning of s t =cking feature on each detector." The ANO-2 CTS does ti e such a note and fore no similar change is required. In addition, the noteA16t found iUREG-1432.

NUREG-1432 Comparison A similar note is not included iR1..EG-1432 SRM 9.2.

1.7 Table 3.3-6, Actions 18 and 19 . "

S'6 These actions reqo mittal , a T the Commission pursuant to specification 6.,,cninn*t *gh range and main steam line radiation monitors when:i::. ration, nnot be mplished. Specification 6.9.2 will be deleted.

However, tt*.~equirement~ submit th*special report will be retained. Only minor wording chah'04;. prop.. .nthe cufl.t actions to delete reference to specification 6.9.2 and to h *"*h.*,itd" be submitted to the NRC. Written comm ation toV4 R is &MRi."in eC 10 CFR 50.4 and therefore, the proposed c..hge*,W '0"* :renc"at r the report be submitted to the NRC. The 10 CFR 50.4

'di'ane ado tely W010Ps that the regional office will receive a copy of the report.

Q.-This is an admir *rtive Abo- ', .., .

ITS Compranri:

ANO-*Ts require 6 special report when the reactor building high range radiation monitors inope* 1. The main steam line radiation monitors were deleted from the ANO-1 TO s'In -onversion to the ITS. The ANO-2 main steam line monitors are in the current liceing bases and will be retained at this time.

NUREG-1432 Comparison Specification 3.3.15 in NUREG-1432 includes a requirement for the containment building high range radiation monitors to be operable. If inoperability occurs, the NUREG requires that a special report be submitted within 14 days in accordance with NUREG 1432 specification 5.6.7. The proposed change to the ANO-2 TS retains the currently approved allowance for submittal of the special report within 30 days. NUREG-1432

Attachment I to 2CAN0103XX Page 6 of X does not include a specification for the main steam line radiation monitors. These monitors will be retained in the ANO-2 TSs at this time.

1.8 Post-Accident Monitoring Instrumentation, Table 3.3-10 The phrase "pursuant to specification 6.9.2" will be deleted in Actions 3.b and 4.b. See DOC A6.

ANO-1 ITS Comparison S... ....

The actions associated with Post Accident Monitonrd!X.."tumaat ion contained in ANO 1 ITS 3.3.15 require a submittal of a special repqrt then trumentation cannot be restored. Therefore, the proposed change i 4istent with th" uirement contained in the ANO-1 ITS.

NUREG-1432 Comparison Ad - o 1 NUREG-1432 includes an optional reporting' nt*.e.ii 5.6.7 related to Post Accident Monitoring Reports. The NU1p-1432 specfi - will not be adopted. The ANO-2 current license basis allows inowthn 30y, which differs from the 14-day reporting requirement in the N tG.o chanropose -day allowance. alloance.g ** *** prpsd to the CTS 30-a 1.9 Steam Gener*o' :* ... ' re 50"45 19 tmS rveillanc ments' Rs) 4.4.5.0, 4.4.5.1, 4.4.5.2, 4.4.5.3, 4.4. Tables- 4-1 and ..,2 A Steam Note Ge statotor Tube S 'ce Pr, m will be added as PTS 6.5.9. The current which TIMit i::":::"* .. i1;*'evc

..m .... orr , -. N wf.e.c.iqR

.the hervice inspection do not apply durin during the "ste*,,t tor **i*nent out._ 4)." will be deleted as the steam generator me already occurred. The current TS Table 4.4-2 requires

-*bmittal of ec?"aeciart to the NURC pursuant to specification 6.9.2. Steam

%81 ~enerator reporn uij.qernts contained in current TS 4.4.5.5 will be relocated to ication 6.6.7NI$pec~iit'n 6.9.2 2ili be deleted and, therefore, the reference in PTVF~ble 6.6.5.9-2 ]1 be changed to reflect the new Specification 6.6.7. See Markup Of and C ANO-1 IT omi :n ANO-1 has re*icated the SG tube surveillance program to specification 5.5.9. Due to the two units being different, the current licensing basis varies slightly. ANO-2 is relocating the current licensing basis with only the minor changes.

NUREG-1432 Comparison NUREG-1432 specification 5.5.9 contains a reviewer's note specifying that the current licensing basis for the SG tube surveillance program should be relocated to this specification. ANO-2 is relocating the current licensing basis with only minor changes.

Thus this change is consistent with the NUREG.

Attachment I to 2CAN0103XX Page 7 of X ANO-1 ITS Comparison (Reference to CTS 6.9.2)

ANO-1 ITS includes steam generator reporting requirements in specification 5.6.7. The ANO-2 proposed change is consistent with the location of the special reporting requirement contained in the ANO-1 ITS conversion. However, based on the reviewer's note contained in NUREG-1432 (see below) the exact format of the ANO-1 conversion is not adopted.

NUREG-1432 Comparison (Reference to CTS 6.9.2)1 Steam generator reporting requirements are contai SiC cation 5.6.9 of NUREG 1432. The specification contains a reviewer's nt t stateReports required by the Licensee's current licensing basis regardin*_ team geneht tube surveillance requirements shall be included here." Thee".. posed change ,M ansistent with the guidance contained in the reviewer's noteAY '1-ý 1.10 Steam Generators, TS SR 4.4.5.5 The Steam Generator reportin-uirements ki rlocated to PTS 6.6.7. See DOC A20.

ANO-1 Comparson ANO-1 ITS 5.6.7 this re ria .uir"r@. The ANO-2 proposed change differs from the. hIPoweve nsistent wit the currently approved ANO-2 license basis .4id-tonsiste "ith the r er's note that is contained in NUREG-1432.

NUREG-1432; D)a-s*.*{-*,.

NLJRE peition 5.69.~~e the SG Tube Inspection Report. A V.. Wer'SW .stat.Ž4Reports required by the Licensee's current licensing basis kding stea

... net vnbe surveillance requirements shall be included here. An

.2ppropriate admirf ,t* ols format should be used." The proposed change to the

"%NQ-2TS is consit with current licensing basis and is, therefore, consistent with th ewers note WIained in NUREG-1432.

1.11 e rihg yCore Emerg System, TS 3.5.2 and 3.5.3 The phraseL Commission pursuant to Specification 6.9.2" will be changed to "to the NRC." Se OC A6.

ANO-1 ITS Comparison ANO-1 CTS did not require a special report in conjunction with ECCS actuations nor does the ANO-1 ITS conversion require a special report. Therefore, the ANO-1 TSs and ANO-2 current licensing basis differ. This is a requirement of the ANO-2 current licensing basis and will be retained.

to 2CAN01 03XX Page 8 of X NUREG-1432 Comparison NUREG-1432 does not require a special report associated with ECCS actuations. The report is contained in the ANO-2 current licensing basis and will be retained.

1.12 Containment Isolation Valves, SR 4.6.3.1.4 This SR will be relocated to PTS 6.5.16. The wording in S .3.1 will be changed to state: "The containment purge supply and exhaus:Ijblation valves shall be demonstrated OPERABLE as specified in the Con.1ent Leakage Rate Testing Program." See DOC Al.

ANO-1 Comparison The relocation between of ANO-2 SR 4.6.3.1.4 r W nsistency io the ANO-1 and ANO-2 TSs -1 th o s ra Ts. ANO- 7 states that ,1sshall be leakage rate tested once." ANO-2 will na ,opt .. d once. Th of "once" could be misunderstood since it is possible a one test may be required due to finding an excessive leakag eate. Incluslot-i The word "once" may give a false sense that only one test is req~t refore, A . 11not include the word "once."

NUREG-1432 Comparison NUREG-143 sp45.5.16 relatd t to 1 doe 1.tncluae the testing requirements related to the c i.m. hrif Rge sup exh i lation valves. Relocation of this requirement f Nt .".4 does change the intent of the NUREG section. It consolidateii16 testing requtements ir location.

1.13 Control Room onira. n., Conditioning System, TS 3.7.6.1 allWNt n n ions d. and e. will be added. See DOC Al, A7, and L3.

.NO-1ITS Comr_

Th 'proposed chang aptures the intent of ANO-1 ITS 3.7.9 and the associated actions and Wim 1. Due "-,the format difference between ITS and CTS minor wording differencesre regi.

The CTS 3 X-. quirements for the CREVS will not be revised to include ANO-1 ITS 3.7.9 note 2, ch states that one train of the CREVS shall be capable of automatic actuation. The information contained in this note is consistent with the currently approved ANO-2 bases for the CREVS, which states the following: "The actions associated with the control room emergency ventilation and air conditioning systems ensure that the remaining train is OPERABLE, that no failures preventing automatic actuation will occur, and that any active failure will be readily detected." Therefore, the note is not necessary in the ANO-2 TS.

ANO-1 ITS 3.7.9 action F (CREVS) and ITS 3.7.10, action E (control room emergency air conditioning system) require entry into TS 3.0.3 if both trains of the respective

Attachment I to 2CAN0103XX Page 9 of X systems are inoperable. The proposed change to ANO-2 TS 3.7.6.1, action e is consistent with the logic presented in these ANO-1 specifications.

NUREG-1432 ComDarison The proposed change captures the intent of revision 2 of NUREG-1432 specification 3.7.11 and the associated actions and note. Due to the format difference between ITS 14J rr nnnrC

1. -4.r;.. .cAW .na a .m~A, 1r a"II II* IIIIIl" V1 UIUI"VI* UIII* t-w I 0,1* v1 IIw* UI!

1.*. .

NUREG -1432 Specification 3.7.11 does not contain a 'similar to the ANO-1 ITS note 2. Therefore, the proposed change to the AN Os consistent with the intent of NUREG-1432.

NUREG-1432 Specification 3.7.11, action 3.7.12, action E require entry into TS 3.0.3 if no n or air conditioning systems are operable. The p captures the intent of these two NUREG,14"i 1.14 Control Room Emergency Air Ftion Syst, The requirements of this SR wift Program (VFTP). See Markup sert% ' I C AVM'. A4, A8, LAI, LA2, M2, and M3.

.. .... c' W

1.15 SR 4.7.8.h

.10.2 will be deleted. See DOC A9.

1.16 i.ral Integ rity, TS 3.7.12 The ref cation (*.9.2 will be changed to direct the submittal of a Special Report DOC A6.

1.17 A.C. SourcesY8 3.8.1.1 A new action "f." is being added and the pages are being reformatted which resulted in moving several actions from the page they are currently on to another page. See DOC Al, L4, L5, M6, and A10.

1.18 Sample of Diesel Fuel, SR 4.8.1.1.2.b

Attachment I to 2CAN0103XX Page 10 of X This change deletes the current surveillance requirement and implements fuel oil testing requirements in accordance with a new program requirement which will be PTS 6.5.13, "Diesel Fuel Oil Testing Program." See DOC LA1.

1.19 Electrical Power Systems, Shutdown, TS 3.8.1.2 A new action ub." will be added. See DOC L4, L5, M6, and A10.

1.20 Fuel Handling Area Ventilation System, SR 4.9.11.2 This SR requires that the fuel handling area vet .i system be demonstrated operable by performing various tests on the HEPA It aal adsorbers. The proposed change will relocate these testing requir ents t S 6.5.11, "Ventilation Filter Testing Program." See DOC Al, A2, , and L1.

1.21 Responsibility, TS 6.1 The proposed changes delete the specific' rence 1AflO-2 and make er preferred wording changes. See DOC Al and A13. "

1.22 Organization, Offsite and Onsilef.11 Mnizations T" , 1 The proposed changes delete thU"lecifi'64fnce tc 2 and make other preferred wording changes. See DOC Al aRIN-. '

1.23 Organization, U*rg' -. ,T$2 2 The propos ig*: ange *reorizes the V-on and provides clarity for the ANO site. In addition, many.p the -. r ments

. "being removed because they duplicate requirements pr*&'kted.in "fhodC&-

lhG Regulations. See DOC A, All, A12, L6, arq&7J. 1o see bie ussion of1iff ,ces numbers 5, 6, 7, 8, and 9.

1.244ffr'bift Staff Qual ons,$..3. 1 th,,proposed charb:e ma inor preferred format changes and replaces the ANSI re~rement that is r4 fenced with a different ANS requirement. See DOS M7 and Al.

1.25 DelIete .6 4 The currentf flfbd section will be replaced with the PTS section entitled "Procedures."

See DOC AI.

1.26 Programs, TS 6.5 The statement "6.5.1 through 6.5.6 will be used later." will be deleted and new programs will be added. For the changes to each of the programs in sections 6.5.1 through 6.5.6, see DOC Al, A3, A16, and LA4.

1.27 Steam Generator (SG) Tube Surveillance Program, PTS 6.5.9

Attachment I to 2CAN0103XX Page 11 of X The SG Tube Surveillance Program is being relocated from TS 3.4.5 surveillance requirements. The proposed changes include preferred numbering and reference changes. In addition a note is being deleted that refers to the steam generator replacement outage. This outage has already occurred and the note is no longer applicable. See DOC Al.

1.28 Secondary Water Chemistry, PTS 6.5.10 The Secondary Water Chemistry Monitoring program is cu y contained as a license condition. The license condition is being deleted and a&gprogram established with the addition of PTS 6.5.10. Minor preferred numb' nd wording changes are proposed to the wording that was included as the Iiition. See DOC Al.

1.29 Ventilation Filter Testing Program (VFTP), PT$ § I The VFTP will be added and is a combirqa'i')Of the filter testing pr s contained in the control room ventilation system and....fuel handipMrea ventilati tem. See 1.30 DOC A2, A4, M2, M3, and LA1.

Diesel Fuel Oil Testing Progra :ý.TS 6.5.13 A.M. .v This program relocates the te tJ-g' ments fr R A.8.1.1.2.b. See DOC A2, LA1, and Ml. See also the disci'.. n o- frences n,?rs 3 & 4.

A.R.

1.31 Containment Leal@ -eTesting'o TV63-3 This prograr eing rel fro.earrent TS 6.15. SR 4.6.3.1.4 is also being relocated t "ý-part of th program. ,S; OCC A1 and A19.

1.32 Deleted, TS 6 Q1n..

J.T!ei&I'I!*!i*Pe* p ently deleted. See DOC Al.

I afety Limit Viol TS Th.i.ection will be eanently deleted. See DOC All, A14, and A15.

1.34 ProcedUm.ndPr s, TS6.8 The TS will 'bernamed and renumbered as Procedures, PTS 6.4. Several procedure types will be b!eted as they are required by Regulatory Guide 1.33. The current TS 6.8.1.a requires that applicable procedures recommended in Appendix A of Regulatory Guide 1.33 shall be established, implemented, and maintained, therefore, listing specific procedure types is unnecessary. See DOC Al, M8 and M9.

1.35 Deleted, TS 6.8.2 and 6.8.3 These will be permanently deleted. See DOC Al.

1.36 Programs and Manuals, PTS 6.5

Attachment I to 2CAN0103XX Page 12 of X This new section will be added and will result in the relocation of several programs to this section. See the individual programs for the associated discussion of changes.

1.37 Radioactive Effluent Controls Program, TS 6.8.4.a This program will become PTS 6.5.4. Minor preferred wording and numbering changes are proposed. In addition a statement is being added that allows the provisions of SR 4.0.2 and 4.0.3 to be applicable to this program. See DOC A-iU*hd A16.

-V 1.38 Component Cyclic or Transient Limit Program, TS 6.86 ..

This program will become PTS 6.5.5. Mino peerred '1ingand grammatical changes are proposed. See DOCAl. Al.4.

1.39 Reporting Requirements, TS 6.9 These requirements will become PTS 66" be DOA-i, LA2, A17, Al, , L9, A20, LA3, and A21. *

1.40 Deleted, TS 6.10 11Q, This section will be deleted permp kOCA 1.41 Radiation Protect . m, T "..,J-0 The requireex 'to have cedure ..r the Radiation Protection Program will be relocated tW*e 6.4.d.

1.42 Deleted, TS 6.143W 3'.hs sec-i-5tt ill eted permanently. See DOC Al.

1.4 3t High Radiation 1*1T 6,,?

THI-skection will be ocated to PTS 6.7 and re-written to adopt some less restrictive cha=nti .See DC :and L10.

1.44 Qffsite Dds-Ca. n Manual (ODCM), TS 6.14 This program mnual will be relocated to PTS 6.5.1. Minor preferred wording changes are proposed. In addition, a change to the ANO staffing organization is reflected. See DOC Al and LA4.

1.45 Containment Leakage Rate Testing Program, TS 6.15 This program will be relocated to PTS 6.5.16. In addition SR 4.6.3.1.4 will be included in the new program. See DOC Al and A19.

Attachment I to 2CAN0103XX Page 13 of X

2.0 PROPOSED CHANGE

The proposed changes for each CTS requirement are separated into the following categories:

Desionator Cate-gorv A ADMINISTRATIVE- Changes to the Current Technical Specifications (CTS) that result in no additionalI. reduced restrictions or flexibility. These changes are tred in aggregate by a single No Significant Haza -riosiderations (NSHC).

MTECHNICAL CHANGES - MORE RESTRICTV hanges to the CTS that result in added restrict reduced flei . These changes are supported in ag il by a single NSRO.%

L TECHNICAL CHANGES -zLESS RESTR.TIJVE - change.tl e CTS that result in reduced rds' .onsp ded flexibility. E*&i corresponding evaluation is s.- 'ed corresponding evaluation suppr,%n*g a finding of~t*.

LA TECHNICAL CH AtRMV QEDETAILS - changes to the CTS that eaim **.@.d reloct detail to a licensee controlled documerZ1ypic'1t invoIi*.tails of system design fundct oioSn'thods of conducting a s w Iphsted in aggregate by a Nt.ch..te bN.= !- *,, . **

.. ht tha no ar cosisent- nedDOD. .... .......

....,e Nee'd to esure..; Ihnge0 sjsfie.~

,* S

NEq

Attachment I to 2CAN0103XX Page 14 of X Administrative Al The designated change represents a non-technical, non-intent change to the Arkansas Nuclear One, Unit 2 CTS. made to make the ANO-2 Proposed Technical Specifications (PTS) consistent with the ANO-1 TSs or the CE Standard Technical Specification (RSTS), NUREG 1432, Revision 2. This change does not alter the requirements of the CTS or RSTS. Examples of this type of change include: wording preference; conventipp adoption; editorial, numbering and formatting changes; and hierai4).structure.

'1 111 A2 A statement regarding the Applicability of SR 4.0Zandd.r SR 4.0.3 is added for clarification that the allowances provji yi* general Surveillance Requirements are applicable toqh . ent g ram. This is an administrative change since the CTS 4:g21nd 4.03 are ntly applicable to the requirements being m~fo the program thm be identified in the Administrative ContrpI1&tion 6.0. This ae applicable to CTS 4.8.1.1.2.b whicR1Ue incorpoed into the ie1uel Oil testing Program, PTS 6.5.13. Theft.h'ge is.. plicable to Cf"*

4.7.6.1.2 and 4.9.11.2 which will be incorP.R. o the Ventilation Filtration Program, PTS 6 ,~1.

A3 The Secondary Water Cheg 4'ifnitoring an"di'Primary Coolant Sources Outside ContainmeftlcensgWiions moved to equivalent programmatic requjrements in-t..S Sec.0 w o...o s and Manuals.

The requires t1,ese licewoqons 1. Iretaine in Section 6.5.

The PTS p mm !d s onol specifications are consistent withs iNURV1432

x " .'"Cen-se.* conan&~rrent d*i*.'--

ý -i-i$**: plai fl.ractice,

... and meet the intent of the existin*jense condi . As sucf his change in presentation of existing requirem hts purg*.*.",mnistrativeA.

A4 2t & 4.9.11.2.a;IT6 6.5.11, Ventilation Filtration Program.

rT6**$*SR76

. q'The pre*. tio.n .61,e requirements for ventilation filter testing is revised for consistl*1 IXf uencies and methods are replaced by a reference to O'N. perform the .... g atbf.equencies specified in Regulatory Guide 1.52,

&Revision 2. Si*r there9 'no actual changes in the frequencies, this Mange lf* is consi erd istrative i* *ture. to be one of presentation only, and there, A5 Licen G~iin 2C.(6) requires an established program to ensure the ca aili t~urately determine the airborne iodine concentration in vital areas un acident conditions. NUREG-1432, Specification 5.5.3 includes a reviewer's note that states: "This program may be eliminated based on the implementation of Topical Report CE NPSD-1157, Rev. 1, 'Technical Justification for the Elimination of the Post-Accident Sampling System from the Plant Design and Licensing Basis for CEOG Utilities," and the associated NRC Safety Evaluation dated May 16, 2000." Approval of Amendment 218 dated August 17, 2000 resulted in the elimination of the post accident sampling system requirements. Therefore, this License Condition will be deleted and no new TS created. This is considered an

Attachment I to 2CAN0103XX Page 15 of X Administrative i _ administrative cleanup related to the approval of Amendment 218.

A6 Specification 6.9.2, which requires the submittal of a special report to the Commission if various systems cannot be restored, will be deleted and thus the reference to it in various specifications will be deleted. Written communication to the NRC is described in 10 CFR 50.4 and therefore, the proposed change will only reference that the report should be submitted to the NRC. Guidance in 10 CFR 50.4 adequately ensures that the regional office will receive a copy of the report. .V A7 An additional Action will be included in TS 3.7.6.t t entry into LCO 3.0.3 if both trains of CREVS or the control roo erg.I c.y. air conditioning system (CREACS) while in Modes 1, 2, 3, orX..4iis is e2R~i.'ent to the CTS requirements and is needed as an eit" condition oriT*,. W.to differences in the implementation. ." ,

A8 PTS 4.7.6.1.2.c directs performancdf* ontrol Ro `.fmergency V"lttIation filter testing in accordance with the Vegt.f on FXesting Program *

(VFTP). This change is administrative. ' .14Tfk7

.2.b, c, d.1, e, and f, which directed performanp.,ffilter testing>ile relocated to PTS 6.5.11, the VFTP. The PTS 4.7.61 2 ..suresthe rj rements of the VFTP are performed. , 4...

A9 Surveillance Requirement 4.7:eh refers :caU. 6.10.2, which was deleted from & m. -2TSs wi 0nmentO e reference to Specifica left in SR 4.7.8.h. The proposed change*.M..*'elete the *rence to cification 6.10.2.

A10 PTS 4.8.14.4 an T4S.*.4 : vjde the administrative direction

.g$s~p iated ~r*~iA ~j~ .2~

All g removed from the PTS since it duplicates requirem the regulations. Such duplication is unnecessary and results ive burden to revise the duplicate TS

,when these re ins revised. Since removal of the information

'Imults i no change in the requirements, removal of the duplicative in ation is dered an administrative change. Further, change to the requpents e controlled by the NRC.

CTS Lo Duplicated Regulation 6.2.2.b 10 CFR 50.54(m) (2)(iii) 6.2.2.c 10 CFR 50.54(m)(1) and (m)(2)(iii) 6.2.2.e 10 CFR 50.54(m)(2)(iv)

Table 6.2-1 10 CFR 50.54(m)(2)(i)

Table 6.2-1 Note

10 CFR 50.54(m)(2)(iv.

6.7.1.c 10 CFR 5036 .. I 10 UP.R n 79 =ni I 10 CFR 50.73 6.9.1 10 CFR 50.4 6.9.2 10 CFR 50.4

Attachment I to 2CAN0103XX Page 16 of X Administrative I 6.9.5.3 10 CFR 50.4 A12 CTS Table 6.2-1 currently contains the requirements that are proposed to be located at PTS 6.2.2.a. This Is an administrative change that simply relocates the CTS information. Otherwise no change is proposed.

A13 There is only one plant manager between the two units, thus there is no need to designate the specific unit, i.e., ANO-2. file A14 CTS 6.7 will be deleted. CTS 6.7.1 .a is redundant t- M.lOrmation included in Section 2.1, Safety Limits.

A15 CTS 6.7.1.b requires that the Vice Presiden..O~g rations -be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of violating a safety limit. is Z!-hotification nistratively controlled as part of the ANO correctiv.n process and wiIV-e>,leted.

This notification is not required to en. ny of the our criteria lif-t&n 10 CFR 50.36. The administrative corif ,L* section .o .chnicalSpecifd ns.s is described in 10 CFR 50.36 as repo D whatitessarvto operation of the facility in a safe manner M is noification will continue to be performed rt of the sa practices for notification, it does not assure the fac . .ted in a saY.nner. Actions taken in the control room by the co ro* rators the safety of the facilty.

A16 PTS 6.5.4 -*.t regardl 110 .1"plicati~.fSR 4.0.2 and 4.0.3 will be ado.d>This isit-tmnent tent with the intent of performing periodi t '....* W" illances. **ce ::*:: no , c'_"ge "44. to regulatory requirements is made this c i considefedadministri--ve.

A1 Q .T.9.1.4"' *T. . :-.' -. ,,.,.........

i.... ....... ^, .... .

A17 ,*T. 6...9.1.4~T"~ttio*n-P*1.introductory paragraph into CTS

,ich W es a listing oft required annual reports. The paragrail. bed ed with the submittal date moved to the individual report. Tfhlw14dvidubQ orting criteria adequately describe the required

";. ,data and theme. this iagraph serves no purpose.

A18 4 PTS 6.6.1 - Th pose d change will reflect the correct 10 CFR 20 M irology foq- units of occupational exposure. The change will also updi#'he re.f.6i~ce to the correct part of 10 CFR 20 (changing 10 CFR 20.407j IQ g. R 20.2206). A statement limiting the report scope to those person itored will be added as a statement of the obvious. Lastly, the pocket dosimeter will be revised to refer to a pocket ionization chamber and the electronic dosimeter will be specified as an additional means of collecting the exposure data. These changes are considered purely administrative since they result in no relaxation of requirements, result in compliance with 10 CFR 20, more accurately reflect the principal of operation of the pocket dosimeter, and acknowledge industry usage of advanced dosimetry devices. These changes are consistent with 10 CFR 20 and NUREG-1432.

Attachment I to 2CAN0103XX Page 17 of X PTS 6.5.16 - The "u0.60L.ý" and "*50.75 L." limits for acceptable reactor building leakage will be revised to "<0. 60 L," and "<0.75 L;"for consistency with the acceptance criteria provided in 10 CFR 50, Appendix J. Therefore, this change has no impact on application of the regulations and is considered administrative.

PTS 6.6.7 - The proposed change relocates in CTS 4.4.5.5 CTS 6.9.3 will be revised to reflect the reporting requirements consistent with 10 CFR 20 and minor editorial changes. These cb s are considered purely administrative since they result i "I*Qlaxation of requirements and result in compliance with 10 C _W These changes are consistent with 10 CFR 20 and NUREG-1432, ..1.2 ..

Attachment I to 2CAN0103XX Page 18 of X TethnknI Chnne - MorA RAtritfiv M1 CTS 4.8.1.1.2.b will be revised to include testing of new fuel oil. Immediate confirmation of fuel oil quality by monitoring for specific gravity, viscosity, and appearance (see DOD 3), as well as follow-up confirmatory testing within 31 days after adding new fuel oil to the bulk storage tank will provide added assurance of acceptable fuel oil. This board spectrum testing will not be routinely performed (refer to DOC L1) since this initial yrification provides the necessary confirmation of fuel oil quality. .,..ýMls an additional restriction on the unit.

M2 By deleting the specific Regulatory Guide (RGj..2s, tn references from CTS 4.7.6.1.2.b and 4.9.11.2.a, the associated S .11 will ensure all applicable RG 1.52 filter testing.I-*encies and crn are applied to the TS ventilation filter systepi 1 This results in a m*ee'estrictive change to unit operation, although R 2 testing not specificaly ailed in the CTS has previously been inc6Wjted withirn,%h. ANO filter te;*g program. RG 1.52 criteria not containu thn *tS includes the a'flow distribution test (when maintenance actfti e'P have affected the air flow distribution) for the ContrIo,m Emergen ntilation System, and the charcoal absorber leak tesd3O.kW* g charcoa ling activities (when the effectiveness of the charco*(

b ymay hav pen affected) for all TS ventilation systems. These tare i..r.

.e.f. as applicable,

.d, under the filter testing prograri5tANW*' -* %

M3 CTS Table4:6, Ati 0 provi&tions for inoperability of one channel of contr1liI. isolatio~n high rajtion. After 7 days of inoperability of one ch1.hel the actio ws an a( nal 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months to initiate and maintain 6rio is Chours -omyenlMentidSystem (CREVS). This additional ours is Age. This time period is eo xiv fn of CREVS er, most problems can be restored Ax'wiithlin* h]tial Ys. If the isolation instrumentation is not restored, the

actuation EV nasily be implemented within the initial 7 days.

M k.dditional app6ate Colitions are included for the control room isolation

high radiatioi statement was added to Actions 17 and 20 to provide ippropriate, ault condition (to be in HOT SHUTDOWN within the next 6tionrs thand OWN in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ) if either Action is not r M i.thw- everting to Limiting Condition for Operation (LCO) 3.0.3.

This is R"I" Ored a more restrictive change since CTS Table 3.3-6 Actions 17 and 26%~ not provide these actions and less time is provided to take the Actions than if TS 3.0.3 were entered.

Attachment I to 2CAN0103XX Page 19 of X TechnicalChanges --More Restrictive M5 CTS Table 3.3-6, Action 21 will be included to provide an appropriate condition if the LCO is not met during movement of irradiated fuel assemblies. Per Note 2 on Table 3.3-6, the control room ventilation intake duct monitors are required to be operable in Modes 1, 2, 3, 4, and during handling of irradiated fuel. CTS Actions 17 and 20 provide guidance for each of these applicable modes. The proposed change NI! create a separate Action for during handling of irradiated fuel and-I,"s the proposed change is considered more restrictive since less tim~ej posed in Action 21 than was allowed by Actions 17 and 20.

M6 CTS 4.8.1.1.2.b does not require sampling q '

-the storage tank. A new diesel fuel oil teatn 5$ogram is pr~ s PTS 6.5.13 and includes a requirement to S1.fp?9 new fuel oil (s.eod Markup of Inserts). PTS 4.8.1.1, AcbA. and PTS 4.8..2.b.3 . How 30 days to restore stored fuel oil prope- etl the new)"at oil has beer d to the storage tank and the new fuel oil s"ple rs re outside the ll'its specified by the diesel fuel oil testing prsampling of new fuel oil prior to addition to the sto*. tanks provi eans of determining whether the new fuel oil is e propriate *

-1jep and has not been contaminated with substan* thatt*j.td have art imediate detrimental impact on diesel engine opefifon. A016-nally, tWEion is included to provide a limitedlj$.etoration tiQ~in thq-, ,L fuel is added and subsequent f new fuel 6-if a covee140"be out of limits. This is an additio ANO-I1V -On...cti opera* ionsistent wih NUREG-1432 and the M7 PTS6.3.wtb uP.tediafl~ct thli!test changes to the Quality Asnzrance P M anQ:

r:.* aproved by the NRC on November 6, W*a*TA N .o..893). Unit sta.f cuahfications are revised to reflect

->commints e.ANS to 3.1-1978 (in lieu of ANSI N18.1-1971).

- Additiona ie d education requirements are imposed for certain

- - " * :,pperation.

positions duedtithis cR . This change is an additional restriction on unit MB PT$6.4.d - Re.A"iements will be included to provide procedures for each of thge ramsid ified in PTS 5.5. The programs included in this section are bat quirements in the CTS. The proposed change is consistent with the t4UEGs and is an additional restriction on unit operation.

M9 PTS 6.4.b - This is a new requirement to maintain the emergency operating procedures in accordance with the requirements in NUREG-0737 and NUREG-0737, Supplement, as stated in Section 7.1 of Generic Letter 82-33.

ANO-2 currently maintains these procedures as required by these documents.

Attachment I to 2CAN0103XX Page 20 of X Technical Chanaes - Less Restrictive LI CTS 4.8.1.1.2.b will be revised to require the periodic testing of stored fuel for particulates only, replacing the periodic testing per ASTM D975once every 92 days per PTS 6.5.13.c. Refer to MI for added testing requirements. This change reflects industry standard acceptable diesel generator (DG) fuel oil testing programs reflected in NUREG-1432. Over the storage life of ANO-2 fuel oil, the properties tested byM.STM-D975 are not expected to change and performing these tests o/n.p -he new fuel oil (see DOC Ml) provides adequate assurance of the fý quality fuel oil.

The periodic testing for particulates monitors a pa that reflects degradation of fuel oil and can be trended to pr n ed confidence that the stored DG fuel oil and can be trended tbiroviderN1psed confidence that the stored DG fuel oil will su-rt SG opera`-1.W L2 It is proposed to add Note 6 to CTS Thbl&4.3-3. The note providd$lree (3) hour time period with the monitor erable to *b)duct the CH.A L FUNCTIONAL TEST without enteringi Associ Actions. This

allowance is based on an industry avera ff me for conducting the test and the need to cond4-,the teat dudr itions for which the monitor is normally required to be A L.E. Whe prming the channel functional test on the radiati" 0i1io- the mo intended function of isolating the control room antartn n propr eergency ventilation demonstrted. is*there ism srn~utictntpcarertr L3 The reqi- ents of CI 3.7.6.1 Wi*1be revised to allow the control room bound Aj.tbe open 6termittentRysOder administrative controls, and to allow bo l4EVS trAs)ej.opeN)te for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months if due to a control roo boun Ad-& 5b1Iity ion is not allowed by the CTS, and OP..ult iSnlr etry into the reements of LCO 3.0.3. Requiring entry 4 no L'01condition

.3 fin is excessive, as it does not provide sufficient ..9itatft-iip a repair. The proposed change is acceptable

because of Jow pr6W ity of a design basis accident during any given

%2,4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months periodo becaUSe entry into the Condition is expected to be very 1nfrequent. TheM! owance to have the control room boundary open

'1r=&mittently isp eptable as the administrative controls that must be im~fbmented 4fl[* nsure that the control room boundary can be rapidly close 9 ed for control room isolation is indicated.

Attachment I to 2CAN0103XX Page 21 of X Technical Chanaes - Less Restrictive L4 PTS 3.8.1.1, Action f.1 and PTS 3.8.1.2.b.1 will allow the fuel storage tanks to contain less than 22,500 gallons of fuel for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months as long as the volume of the individual storage tank is greater than 17,446 gallons. When the volume is between 17.446 and 22,500 gallons, only the storage tank will be declared inoperable, the diesel generator will remain operable.

Therefore, the PTS will allow an additional 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to ret.ore the level prior to declaring the associated diesel generator inoperablpe..ah fuel oil storage tank, when 100% full (22,500 gallons), conta1n6ufficient volume for approximately 3 %days of operations. Thereforeh . bined storage capacity, 45,000 gallons, ensures a sufficient s....o oil for seven days of full load operations. Only one diesej.ge1ator is'4red to supply the components needed for accident mitig-Q'p The propoe ange introduces a lower volume of 17,446 ga '. This value, wheU.' rmmed with the contents of the other storag (i.e., a total of 34,982 -n,s) ensures six days of fuel oil is availa The 48 houm allow adequai Cti e to get a tanker truck to the site, perfor e req 0ampling, and reore the volume. During the proposed additil i sociated with the reduced level, the diesel werator is cap a-""'Performing its intended function and is therefore nt..trable. The il volume may be less than desirable for this sh rif -e.othe loIbability that an event would occur for which the die i gened fould btuired.

L5 PTS 3.8.1.1,Ationt.2-and PTS.:.88 `2%.2 w&i.-WX an additional seven (7) days to re s`tm,`the stOW, fuel oil*

articulates *o be within the required limits pr-A&declaring',*P associa diesel generator inoperable.

Normaltylnding ofg~ticulate lev' otllows sufficient time to correct high particulaf :1iivese prio ang th.)Mit of acceptability. Poor sample c .e* pment, and errors in laboratory

's*n p ....... failures thaPi*ot follow a trend. Since the presence padoes c wt mean failure of the fuel oil to bum properly in the diesel eng,,;,An pR late concentration is unlikely to change

.,-. significantly een sug.eillance intervals, and proper engine performance

,jias been receAi jdemoirtsrated (within 31 days), it is prudent to allow a bjef period po0 declaring the associated diesel generator inoperable.

'T* day ActioK1 low for further evaluation, re-sampling, and re-analysis of the0sel ger146r fuel oil.

L6 PTS 6.2zSwViMl1 allow an individual qualified in radiation protection procedure Ato be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to provide for an unexpected absence. The proposed change is reasonable. A similar allowance is granted to licensed operators and is included in CTS as the #

Note associated with Table 6.2-1.

L7 PTS 6.2.2.g will allow the Shift Technical Advisor (STA) to support the shift crew instead of only the shift supervisor. The change provides more flexibility to the STA and the crew and is consistent with the actual practice of the advisory individual.

Attachment I to 2CAN0103XX Page 22 of X Technical Channes - Less Restrictive L8 PTS 6.2.2.c will allow the STA position to be vacant for up to two'hours in order to provide for an unexpected absence. This will allow needed staffing flexibility. Prior to the approval of TS Amendment 209 (Safety Evaluation Report (SER) dated August 26, 1999), the requirement to have an STA was included in Table 6.2-1 and the associated # Note that allped for unexpected vacancies applied. The two hour allowan!e 4-r'Vacancy was inappropriately disassociated from the STA in Amen#ic 209.

L9 CTS 6.9.1.5 defines the requirements for Occ Mat -sure Data Report. The submittal date for this report wUp.l.vised-uithat the report th~nsistent is submitted by April 30 of each calendarje This chang with the comprehensive revisions to 10Fg*2.. The date of S56)' tVal for the Annual Occupational Exposure p is revised from March 4p~pdl

30. This report is provided to suppr&W'"t the infomi.Ation required I 10 CFR 20.2206(b) which is filed on o fore DKin accordance vth 10 CFR 20.2206 (c). The supplemental 'report submittal date is therefore revised to corret .d to the req uird~ubmittal date of the report being supplemented. g 0-1.

L10 CTS 6.13- The requirementsf9r hig d .0n araWll be revised to include additio:p eviously app.ved.p s1j:qr irnpfmentation of alternates toi ol'o.f devicer dfi sig uirements of 10 CFR 2Q %sese a rliatives pi e adequate control of personnel in high ra&9 ,t areas as~idencedbjNRC issuance of NUREG-1432.

I

Attachment I to 2CAN0103XX Page 23 of X Less Restrictive - Administrative Deletion of Requirements LA1 CTS 4.8.1.1.2.b - This information will be moved to a licensee controlled document such as the Diesel Fuel Oil Testing Program (DFOTP), or the Ventilation Filter Testing Program (VFTP). A description of the programs will be incorporated into the Administrative Controls section 6.0. This information provides details of the method of implementation which are not directly pertinent to actual requirements. Since these det1Is are not necessary to adequately describe the actual regulator .*irement, they can be moved to a licensee controlled document wi f; significant impact on safety. Placing these details in controlled docu en.rovides adequate assurance that they will be maintained. The de bf'. i FOTP and VFTP will be controlled by IOCFR 50.59.

LA2 This information will be moved to a 46Q.-st controlled document sues the Bases, Safety Analysis Report (SARV,ýp..".4APM, Teo reme4 Manual (TRM), etc. The information pr`-".des de ;f design or prod~s which are not directly pertinent to the acMuI ment, rWY i.e., Definition, Limiting Condition for Operation, or Surveilt Requirement, but rather describe additional unneces ..ptails such -hii acceptable method of compliance. Since these didiail; t ne adequately describe the actual regulatory require tt ... a licensee controlled document without ia-f`'U .- on fty. Placing these details in conte ouments" mv sssurance that they will be maintaini/Th*".e*-ýshi , will b '<ifolled by thABases Control Process in Chap.t~ibf the PTJ$+

CTS L n * 'w Location 4.7.6.1.2

01 , Ba$s, SR 4.7.6.1.2.a 4,7; 6 1.2d.d *

B"ses, SR4.7.6.1.2.b

___ 2-, TRM TRM S6.9.1.3 N .v

Attachment I to 2CAN01O3XX Page 24 of X LA3 CTS 6.9.1.5.c - The reporting of these challenges was incorporated into the CTS in response to Three Mile Island (TMI) Action Item I1.K.3.3. This action plan was originally implemented only to provide a venue for data gathering.

There is no plant specific safety basis for submitting routine information on the operations of this particular equipment. Technical Specification Task Force (TSTF) Traveler #258 removed this reporting requirement based on Generic Letter 97-02, "Revised Content of Monthly Opwraing Report" and discussions related to the NRC Performance Ind Program. The conclusion was that this information was not need$4hhe assessment of NRC Performance Indicators and as such t Wrement to include information related to challenges of the pre r ity valves in the monthly operating report was not needed. *NURE~f oes not require reporting pressurizer safety valve ch9 s annually. '-though the NUREG previously required a monthly j of any pressunz rfety valve t1K challenges, Entergy took exception ti*.onthly reporting requi nt in a February 1999 request for a"itnal info~tion related othe administrative controls of the ANO-l NO:W1(reference2). *tergy continued to require the annual re Wisi1posed that the reporting requirement for the pressurger safety va%ý'e deleted. The reason for deletion is consistent wit gic used in -bove referenced traveler even though the reporting ' Jdiffer.

In 1997 with thee*suance of At Q-2 uennt *lt (reference 6),

which addedo *,peraI;otection (LTOP) requirement AAO .mittedtoile within the report of challenges to the premMQiVer safety V.'"es a re f any challenges to the LTOP valves.

~~~......

...'.* ,.v.M:*.. ... -.:

to

.Challengesi-ty valves or LTOP valves that result

'="*tetial I**., 'ion safety woide evaluated for reportability under 10

'C*R

and iv-eported to the NRC.

LAC Where p p ll'pecific management position titles in the CTS will be

$!i, replaced wit peneriAO4jI as provided in ANSI/ANS 3.1. Personnel who fulfill these postkinas ar ill required to meet the qualifications detailed in j proposed Sptification 5.3. In addition, compliance details relating to 14'*plant speci Onanagement positions titles fulfilling the duties of these ge\positigONWill continue to be defined, established, documented and updait9A'ln t controlled document, such as the QAPM. This approach is consir ith the intent of Generic Letter 88-06 which recommended, as a line iten1mprovement, relocation of the corporate and unit organization charts to licensee controlled documents. The intent of the Generic Letter, and of this proposed change, is to reduce the unnecessary burden on NRC and licensee resources being used to process changes due solely to personnel title changes during reorganizations. Since this change does not eliminate any of the qualifications, responsibilities or requirements for these personnel or the positions, the change is considered to be a change in presentation only and is therefore administrative.

Attachment I to 2CAN0103XX Page 25 of X In lsummary Describe associated changes to the Technical Specification Bases, if any.

3.0 BACKGROUND

I1

4.0 TECHNICAL ANALYSIS

[I

5.0 REGULATORY ANALYSIS

5.1 Applicable Re-iulatorv Re uir The proposed changes have been i applicable regulations and requirements continue to be met. I I Entergy has determined any exemptions or relief from regulatory requiremen conformance with any GDC differently than describe 5.2 II whether or not a significant hazards consideration is it(s) by focusing on the three standards set forth in 10 ,"as discussed belowi I. e involve a significant increase in the probability or previously evaluated?

Response

[Explanation/basis for the response.] I Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

Attachment I to 2CAN0103XX Page 26 of X

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

tExplanationlbasis for the response.]

Therefore, the proposed change does not create the possibilit of a new or different kind of accident from any previously evaluated.

3. Does the proposed change involve a significant reduc margin of safety?

Response: No.

tExplanation/basis for the response.]

Therefore, the proposed change does i volve a reducti margin of safety. .. * '

Based on the above, Entergy concludes fthat the prop s;pendment(s) present no significant hazards consideration under the stai*r: ; t forth in, QFR 50.92(c), and, accordingly, a finding of "nosignificant hazards considf* *i stified.N 5.3 Environmental Considerations 2.$.11

d. ........ ---

g- W Ihe proposed ani inent

. doesh $t involve a significant hazards consideration, (ii) a significant change in'thký,types gg.-ff6ift &a.t incr in the amounts of any effluent that may be released offsite, or (iii) %gni.nid h crS'a-mn10 Widual or cumulative occupational radiation exposure. ingly, posed am i meets the eligibility criterion for categorical exc usipj:ef 6*o1iir.i C 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no envi ental impact°. emeruW nvironmental assessment need be prepared in connection it ropose amen t The propose ne:d.:confined to (i) changes to surety, insurance, and/or indemnity requirements, or-c s to record keeping, reporting, or administrative procedures or requirements. Ai.ly, the proposed amendment meets the eligibility criterion for categorical exclusion forth in 10CFR51.22(c)(10). Therefore, pursuant to 10CFR51.22(b),

no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

r-I0 PRECEDENCO

Changes (mark-up)

(i) Containment Radiation Monitor AP&L shall, prior to July 31, 1980 submit for Commission review and approval documentation which establishes the adequacy of the qualifications of the containment radiation monitors located inside the containment and shall complete the installation and testing of these instruments to demonstrate that they meet thj operability requirements of Technical Spec ion No.

3.3.3.6.

2.C.(3)0) Deleted per Amendment 7, 1" 2.C.(3)(k) Deleted Amen "> 12, 6/1 217: ...and Amendment No. 31, 5/12/82. maW 2.C.(3)(1) Deleted per Ame nt 24, 6/1*.8..

2.C.(3)(m) Deleted per Amendme *.* r79.

2.C.(3)(n) Deleted dment7 i 8.

2.C.(3)(o) Deleted per'r end, * *,t72/ ..

2.C.(3)(~)tee~ perAedrnt 3 This will be

~...9~ .. .**..

relocated to proposed TS 6.5.10. See ......

. tc~

. r ca GenRerFator W t e, Markup of .- RGP Mhcct t PI", to manomizc steam ioion insert pages. ~~cnrat~i~bedegrdation. The programn shalb

'defnedif~~ecfic lan prcedresand shall ncluidA-P..

ra.. t-- .. ,. . .....p--.. e atriu ofteProceUrcS used to I

ui measur

3. dcnification of process samm~ino Points.

0 il WGi-roeaureror in rhecording andG managementof 5.Proc~edures definingcorerctiye action;S for oGE control point c-hemistryconditions-; and

6. A prochedure ,de;;tm;f'iR the auth-oty respGn&,ble for the interpretatio* of thedata, and the sequence and timina of Pdadmonstraieo.nt

-e--*J * -- ? "e- S.....

FGGlUrro !ionitiate Gorrect!Yeaction.

IQ 7

7Eo

I %)ý 2.C.(4) (Number has never been used.)

This will be'.

moved to PTS 6.5.2.

See markup 2.C.(5) Deleted per AmendmentEOl shall impleomnt a pr,-,*,m frtm s'ystems rdio-ativ flIM,

dun ,i;,-

levcls. This program. shall inc-ludo the foliov.ig

,^duc. to outside containment that would or could contain h-4"gly lak-ege tran*i*nt or ac-*dent to as low as practical e

of insert pages. 1. Pr-ovisions establishing pro'.'ntatE'e maintonanc- andpridciul im rm "inn + A.,~ei mr ^f~imn This will be a "Mp . nr- h Deleted per AmendmentEG' shall -%"W permanently 2.(

deleted. capability to accurately dcto~ino th0fime iod;ne nFn Y*.- I e S ~

areas uindernaccident

, . , ,, , , codtos spo ,, "". :

rftzshal in~k&~efloig

1. TrFaining of personnel,

2. Poccdrcsfor onionfl,-A i

'n~

2.C.(7) Deleted per Amend (8) Antitrust Conditions . .

EOI shall not ma as pow - 'gy rom <ansas Nuclear One, Unit 2.

Entergy Arkans Jic.is r Qnsible %ccountable for the actions of its agents to the extent sad::int's actiojisaffect th .rketing or brokering of power or energy from ANO U~i~

(9) W. Ave ra&

....od. e Bumu_RI '

erasI'tis ' authorized to operate the facility with an individual rod averagge I bum, pN(.umup averaged over the length of a fuel rod) not to

exceed 60 awatbys/kilogram of uranium.

X.~

D. Phv Protection EOI shai.fty W"lent and maintain in effect all provisions of the Commission approved p security, guard training and qualification, and safeguards contingency p ~hs, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plan, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Arkansas Nuclear One Industrial Security Plan," with revisions submitted through August 4, 1995. The Industrial Security Plan also includes the requirements for guard training and qualification in Appendix A of the safeguards contingency events in Chapter 7. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

Amendment No.

44,428,4,46-47,47, A

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 R ES PO NS IBILITY ............................................................................................... 6-1 6.2 ORGANIZATION ......... ........... ................. 6-1 6.2.1 Off-ite-Onsite and Offsite Organizations ......... .. "................... .6-1 6.2.2 ,F-aGily-,Unit Staff ............................................... .... 6-2 6.3 UNIT STAFF QUALIFICATIONS ....................... ................ %

6.4 TRAW NG-PROCEDURES ......... . ............... . .. . g 6-3 6.5 DE0MTE D PROGRAMS AND MANUALS . 6-4.....

61 6.5.1 Offsite Dose Calculation4,anuau (ODC' .. 6-4 6.5.

d oR cCoolant 6.5.2 Primary ie E fu .at .or.*. .* a.. .- " *..... Progrm..... .......... '........................ 6

.............................. 6-4 6.5.5 mponC vc Ii. nsen',' Prga....................... &5.

6.5.4 Radioactive ControlS . ..... ................. ........... . 6-5 6.5.5qU*iyo Fit e st Prorgram en ............................................. 6-5 6.5.7 React'olante i F....ee Pro-gram .............ction . Program..............................

.... 6-6 6 514 c.,-t - Bases . on. ro . .... 6-6

.5.6StamentLeaka'g). Tube Surveillance Program ........................... 6-7

10 Secondary *Ve ": tv. Ch .. .. .. .. ....... 6-13 6 51.5 'Vntilation Filt&Testing Program (VFTP)............................. 6-14 6.5.13 DieselFuIO* I T'estingq Program ................................... 6-15 6.5.14 TechniaSpecification (TS) Bases Control Program ............... 6-16 6.5.16 Containment Leakage Rate Testing Program.......................... 6-17 ARKANSAS - UNIT 2 XVl Amendment No. 60,460,

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.6 S.^.FE TY R R R IET . A.^ T ..IGN ................................. e !

6.79 &.r! ROU

_3 54T! E O T ................................ ,, -...*',,,.e !

6.9.4 ROUTINE REPORTS ........................

6..2 SPECIAL REPORTS ...... ..... ... IV, GA.9.34ANNUA RA D EFFLr-. 1T . RT 6 re.11 RA 1A TION PROT-ECTIPR .QM All 6.....

1E.........

6_ F4 O- - y.-N" ..............

6-18

" Occupatia Radiatt* Exposure Report 6-18 6.6.2 nnual RadlibIf ical Environmental Operating Report 6-18 6.6.3 &<aRiOacffluent Release Report 6-18 6.6.4 Montihv.Oerating Reports 6-19 6.6.5 CORE OPERATING LIMITS REPORT (COLR) 6-19 6.6.7 Steam Generator Tube Surveillance Reports 6-21 6.6.8 Specific Activity 6-22 6.7 HIGH RADIATION AREA 6-23 ARKANSAS - UNIT 2 XVII Amendment No. 24-,60,0-,04,467,4-76, 103,

DEFINITIONS EXCLUSION AREA 1.31 The EXCLUSION AREA is that area surrounding ANO within a minimum radius of

.65 miles of the reactor buildings and controlled to the extent necessary by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials.

UNRESTRICTED AREA mv 1.32 An UNRESTRICTED AREA shall be any area at or ",-the exclusion area boundary.

CORE OPERATING LIMITS REPORT 1.33 The CORE OPERATING LIMITS RE is the ANO-2 cume hat provides core operating limits for the W.nt operr reload cycle>-lese cycle specific core operating limits shall be deteqned fi!2 ih reload cycle i '"accordance with Technical Specification 6.6.5645. Pa 141 ion within these operating limits is addressed in individual sp 1.tions.

ARKANSAS - UNIT 2 1-6 Amendment No. 60,449,467,4Q3,

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM/TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION

1. AREA MONITORS

a. Spent Fuel Pool Area Monitor 1 Note 1 < 1.5x10"2 R/hr 13

b. Containment High Range 2 1,2,3, &4 18

2. PROCESS MONITORS

a. Containment Purge and Exhaust Isolation 15 &

cpm 16

b. Control Room Ventilation Intake Duct C.

Monitors Main Steam 2 wte 2

-106 cpm 17,20,21 I Line Radiation 1 1 Monitors 10-10 104 mR/hr 19 Note 2 fuel.

The addition of Note 21 to item 2.b and the All page format change Al from landscape to portrait.

ARKANSAS - UNIT 2 3/4 3-25 Amendment No. 63,430,44-,206,234,

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 13 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 16 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, complete the following:

a. If performing CORE ALTERATIONS or moving irradiated fuel within the reactor building, secure the containment purge syq 'or suspend CORE ALTERATIONS and movement of irradiated fuel:4l HU the reactor building.

b. If a containment PURGE is in progress, se .;t ,pontainment purge system. X

c. If continuously ventilating, verify the G monitor o0e'able or perform the ACTIONS of 3.3.3.9, or secure:!he:ntainment purg yem.

M5 ACTION 17 - In MODE 1, 2. 3. or 4 Wwith no channthin 1 hourB and maintain operation of the control room *i: ency yeffi ation system iVS)i Al the recirculation mode of operation or be if1OT*, DBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN in the followirtiiOtburs. M4 ACTION 18 - With the number of channelsi M.ABLE one iehann required by the Minimum Channels OPERABL . (1) i'.estore the inoperable channel to OPERABýt.ýstatus*i'n.0 day (2) prepare and submit a Special -,to the NIFL

- nt to Spcifirtio 642-within 30 1.* Mp the e *.0liningi f ction taken, the cause of the inope" , and tif.ans an hedule for restoring the system to OPERABL'.,i'jtus.

methods f M"nrainment With I chn inoperable, initiate alternate methosof t

..... g nt p" 5ta.i. entiation level within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in addition to th %ns4&b.bo .

ACTION 19 - W a.....

1, er, -RABLECha s less than required by the Minimum

.hane-- P:..EAB..M*

.. uirements, initiate the preplanned alternate method

. monitoring pM e parameter(s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

. either rest' in 'OrableChannel(s) to OPERABLE status within 7

%:' days of the 4nt, or itea p .. .

2) are and Wbmit a Special Report to the ,.mmissie,,n,.,l .NRC ,t

2) .- 6..2 within 14 days following the event outlining the act I P, the cause of the inoperability and the plans and schedule for re ing the system to OPERABLE status.

than M5 ACTION 20 - <r6-MODE 1 2 3 or Wwith the number of channels OPERABLE one less require y te inimum Channels OPERABLE requirement. restor9 the -o",. 3 tt CFAI =

rchnnnar inr! P ep ,- er7uireme. A-maintain the control room ARKANSAS - UNIT 2 3/4 3-26 Amendment No. 6C,4,3,446,206,234,

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES INWHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED

1. AREA MONITORS

a. Spent Fuel Pool Area Monitor S R M Note 1

b. Containment High Range S R Note 4 .4 1, 2,3, & 4

2. PROCESS MONITORS...

a. Containment Purge and Exhaust Isolation Note 2 R Note 3 5 &6

b. Control Room Ventilation Intake Duct Monitors S 6

/Note Note 5

c. Main Steam Line Radiation Monitors S A*- M 1, 2, 3, &4 Note 1 - With fuel in t%.! elpool bi Note 2- at least8pe Within *h9...... ud ipnor*ii.iating h-ment purge operations and alt per 12 ho duin a inment purge operations.

Note 3- Within 3 gs prior to* 'iating contment purge operations and at least onc ,31 da ntaijnt purge operations.

Note 4 - /ep.table* :1rvided ý. in Table II.F. 1-3 of

10.737 0 Note , D,4 d during handling of irradiated fuel.

Notet.'"l When the'. R Iriol Ventilation Intake Duct Monitor is

-ois iplaced inan inoDerab status'~ely for performance of this Surveillance.

~ ntr into assodhated Acti6hs may be delayed up to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

Page format change [*

from landscape to portrait is Al.

ARKANSAS - UNIT 2 3/4 3-27 Amendment No. 63,43G,445,206, 234

TABLE 3.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Containment Pressure (Normal Design Range)ln 2 1

2. Containment Pressure (High Range) 2 2

3. Pressurizer Pressure 1

4. Pressurizer Water Level 2

5. Steam Generator Pressure 1

6. Steam Generator Water Level 1

7. Refueling Water Tank Water Level 1

8. Containment Water Level - Wide Range 2

9. Emergency Feedwater Flow Rate 1

10. Reactor Coolant System Subcoolin-Margin Monr 1 1

11. Pressurizer Safety Valve Acoustic OR f,"qjndical 1

12. Pressurizer Safety Valve Tail Pipe "1 eeri 1 This page is included as a format change only landscape to portrait. Al ARKANSAS - UNIT 2 3/4 3-40 Amendment No. 7-,43,2G,63,416,423,

TABLE 3.3-10 (Con't)

POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

13. In Core Thermocouples (Core-Exit Thermocouples) 2/core quadrant 1

14. Reactor Vessel Level Monitoring System (RVLMS) 2 3,4 Action 1: With the number of OPERABLE post-accident monitorir,*:;.channels less than required by Table 3.3-10, either restore the inoperable chann1:05PERABLE status within 30 days, or be in HOT SHUTDOWN within the next 1,06s.

Action 2: With the number of OPERABLE post-acciden annels less than required by Table 3.3-10, either restore the inoperab.b.c, annel to'OP..RABLE status within 30 days, or be in HOT SHUTDOWN withinet!ixt 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

If only one channel is inoperable ~ .,ontainme.t entry is re to restore the inoperable channel, the channel n*:,,not be Aitred until the" wing refueling outage. ' -V Action 3: With the number of OP L channelI'Zk. less than the minimum number of channels required to be O .

a. If repairs M are f be in t shannel OWN to OPERABLE status within'b, WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. lf4J ir is not sible ,, shutting down, operations may continue and a ial report 6..2 shall be submitted to the NRC CA6 wi -30 d ofii the i.ure; describing the action taken, the cause of the :ftn..;a. h ii' and schedule for restoring the channel to tutus durin next scheduled refueling outage.

Action , With the ner f BLE channels two less than the minimum channels required to bQ ERA.

"Ifepair, feasible, restore at least one inoperable channel to OPERABLE

" status t wi

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12

b. If ir is not feasible without shutting down, operation may continue and a special report pucnt to ,peifation 69.9.21 shall be submitted to the NRC rA6 within 30 days following the failure; describing the action taken, the cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE status during the next scheduled refueling outage.

ARKANSAS - UNIT 2 3/4 3-40a Amendment No. 89,42-,

REACTOR COOLANT SYSTEM STEAM GENERATORS LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more steam generators inoperable, restore the in 'le generator(s) to OPERABLE status prior to increasing Tavg above 2000F.

SURVEILLANCE REQUIREMENTS .A 4.4.6.04.4.5 Each steam generator shall be demo !ZedOPERABLE in a dance with the Steam Generator Tube Surveillance Program co nofh f augmented inserice pt gram.

IQOTE:= The requirements for inserviee n.o~i, r n~ F~wr- h rcpiacomont1 otG6 21) 4.4.5.1 Steam GeneorWbra tamA g9eneator shallb 4-Slci~itdfl~~inEr determined -PEACDuin AhBL 01nb Cp~a~~cetn&eI-th ao 4.4.5.2 Steam Gcnci~ar,.mp-hb S.eti¶ nd nceci The steam generato tub minmum r~l~sie, nsp~t~ reult~.~ifiatinand the crgresponding action r~equiFed shall bS pcfdnTb111 henservice inspection of steam geneato~'~~hfr~uonces tubs peciiedin specification 4 4.5.3 and

~ tu~~all ezvrifi~a&kneptable per the -acceptance ritaria o

~ifiat~oiA4~,1. h~e bes eleted for eachine'.'iee inspection shall include at tt 3% Of th4Xn mbftbsi al steam generators; the tubes selected for

~ insectins ~flbcs~lPd Mn arandmbsc xet b.~

~ ~ oThe

~~~~~es lccdfrocineve tubes ofrs thel inspertin (sualbequn tom the preserv.ice ins.pection) of each steam generator shall inclu1de:

SR 4.4.5.1 and 4.4.5.2 are relocated to PTS 6.5.9. See markup of inserts.

ARKANSAS - UNIT 2 3/4 4-6 Amendment No. 468,187,2,247,22-3, Next Page is 3/4 4-13

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

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This page will be deleted.

ARKA.NSAS UNIT-2 3A4-4-40 Amm~rndme~t, No

TABILE 1.1 13 MIRflIUM Nt~gRER OF ST-EAl! GENERATORlS TO EE ,;,ETE vUI Przserviee ir.speetlen f Yea Ne. of Steam Ger~er.ters per Unit E'irzitl rZrvi z inspeetizn Beeenel Subozcjuzn n2 nz i Otte' Tal Net~~-& 010 1

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ARKANSAS -UNIT-2

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EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tavc, > 300°F LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each sub-system comprised of:

a. One OPERABLE high-pressure safety injection pump,

b. One OPERABLE low-pressure safety injection py., id

c. An independent OPERABLE flow path capa -t suction from the refueling

ýJ water tank on a Safety Injection Actuation $*nal aii tomatically transferring suction to the containment sump on a ..3;ulation Acti3 Signal.

APPLICABILITY: MODES 1, 2 and 3*.* X ACTION: "

a. With one ECCS subsystem ino #',fe, restore ft perable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in OJ1 I'DOWN, the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. In the event the ECCS is actuated" i t r into eactor Coolant System, a Special Report shall ."pared an 1.,upb rd CQ p ant to S ih C within $8ses he circumstances of the actuation and Iac ated a on cycles to date.

SURVEILLANCE RE J1E MENT" 4.5.2 Amb sy be de R.4ed OPERABLE:

x" At least on_. perli kipurs by verifying that the following valves are in the indicated po Qions " ower to the valve operators removed:

Valve Nu Valve Function Valve Position 2CV-5101" , ' HPSI Hot Leg Injection Isolation Closed 2C.V-51.02 HPSI Hot Leg Injection Isolation Closed 2BS26 RWT Return Line Open

With pressurizer pressure > 1700 psia.

ARKANSAS - UNIT 2 3/4 5-3 Amendment No.

EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tavo <300°F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE:

a. One OPERABLE high-pressure safety injection pump, and

b. An OPERABLE flow path capable of taking suction Jt1fn the refueling water tank on a Safety Injection Actuation Signal and automr.kfly transferring suction to the containment sump on a Recirculation Actuatio ' LhI APPLICABILITY: MODES 3* and 4.

ACTION:

a. Wrth no ECCS subsystem OPERABLE'.store atA-st one ubsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in CO HUT Ne.

b. In the event the ECCS is actuk -:.gnd injects i Reactor Coolant System, a Special Report shall be prepqf.' id. submit A6 Specrifiction 6.9,2-to the NRC th 49t4.s d s bing the circumstances of the actuation and the total accumulated" ;tuati d Ies. t SURVEILLANCE RE NEMENTS;5 W.

4.5.3 The ECCS subsysem Q' dm PERABLE per the applicable Surveillance

Wth priesrzer pressure -10 psI

% * . 4 ,,: '.

ARKANSAS - UNIT 2 3/4 5-6 Amendment No.

CONTAINMENT SYSTEMS-SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.1.2 Each containment isolation valve shall be demonstrated OPERABLE at least once per 18 months by verifying that on a containment isolation test signal, each isolation valve actuates to its isolation position.

4.6.3.1.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pw.uuant to the Inservice Testing Program.

4.6.3.1.4 The containment purge supply and exhaust isol id'Walves shall be demonstrated OPERABLE as specified in the Containment t....*te .. Testing Prog ram.

ZZ PrOO t- exc-eeding onditions building integrity per TS 3.6.lth h

"'k supply andc exhau st isolto "ade h~ evfind to be Amt.+

acce.ptable limits pe T4.165.1" thetzh" tc- encce Al~

rato te of the cona=4rn -purge rS SR 4.6.3.1. 4 is being.......

moved to P'TS 6.5.16.

See PTS 6 markup of changes. .

CIA Joe m~

0.510

&,I

_.. --' .. t ARKANSAS - UNIT 2 3/4 6-17 Amendment No.

46,149,154,214,233

PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6.1 Two independent control room emergency ventilation and air conditioning systems shall be OPERABLE. (Note 1)

APPLICABILITY: MODES 1, 23, 4, or during handling of irradiated fuel.

ACTION:

MODES 1.2.3.and4

a. With one control room emergency air conditioni5ystem inop& e, restore the inoperable system to OPERABLE status wit days or be in 'st HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in QLISHUTDOWN withi ollowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With one control room emergency ventilation y erable, restore the inoperable system to OPERABLE status within 7 days or bi 4*ast HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUt*'WN within the"*o*wing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With one control room emergency ond t systei*.d one emergency ventilation system inope re

'Je M., o le control room emergency ventilation system tq-1 R LE staf t.tERA sarestore the inoperable control room emergency p nditloiIn9 syste OPEFRA1LEtatus within 30 days or be in at least HOT STA within xt 6 s and in COLD SHUTDOWN within the following 30 h'ifr**.

d. With two pontrol romear fur vstems inoperable due to an inoperable contr0ftifftunda' estore the conffidloom boundary to OPERABLE status within 24 hos'W be i6' ast Hf TANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN the followiriti

T~tfifl-:i hou'-'~

e. Wi. coto ., (7

e. vwl ocontrol room eergenMA ventilation systems inoperable for reasons other than actiorfd'.br two control m emergency air conditioning systems inoperable, enter Specifica:igon.0.3. '01 During Handling of aditFuel dr. With one control room emergency air conditioning system inoperable, restore the AlI inoperable system to OPERABLE status within 30 days or immediately place the OPERABLE system in operation; otherwise, suspend all activities involving the handling of irradiated fuel. The provisions of Specification 3.0.4 are not applicable.

es. With one control room emergency ventilation system inoperable, restore the inoperable system to OPERABLE status within 7 days or immediately place the control room in the emergency recirc mode, of operation; otherwise, suspend all activities involving the handling of irradiated fuel. The provisions of Specification 3.0.4 are not applicable.

Note 1: The control room boundary may be opened intermittently under administrative controls. 1L3I ARKANSAS - UNIT 2 3/4 7-17 Amendment No. 206 2

, 19

Qrid K;;'

wci y ~co CL~ w 44#

PLANT SYSTEMS "CONTTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM I-MITING C"ONDITION FOR OPERATIONf~ontinuedi, h . W ,,"Vith one control roo....mme..rgq.cyX..air.,..nd..tJo.n. systerm and one control room emergency ventilationsystem inoperab'e.

1. restore the inoperable control room emerigency ventilation system t, OPERABLE All status within 7 days or immediately place the control room in the emergency recirc A mode of ooeration. and

2. restore the inoperable control room emergency istem to OPERABLE status within 30 days or imediatste t ystem in imndiaeffffi )h e OPERABLE

3. othenvivse, 9.t suspend e......... e alH act-ivites

.".....................................e........ :lvoM

---.............. vi khandlina ptrr&e h nd in ,....... .o".ue. .......

.n

4. The orovisions of S ecification 3.0. ** not ap*ok*te With both control room emergencry, air conditif-o h s or both controjl room emergency ventilation systems i!era.e.. viM A11 susend ail activities involving the hanAing~~jgdiated fuel:

ing. o . .....

-*.;*-*.M* * .,

4 "Aw l9""

to ....

ARKANSAS - UNIT 2 3/4 7-17a Amendment No.

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4Gentinued) 4.7.6.1.1 Each control room emergency air conditioning system shall be demonstrated OPERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS by:

1. Starting each unit from the control room, and

2. Verifying that each unit operates for at least 1 jfl nd maintains the control room air temperature

84 0F D.B.

b. At least once per 18 months by verifying a * '..e of 9900 dm 10%. s4r 4.7.6.1.2 Each control room emergency air .,t .ystem shall be destrafed OPERABLE:

a. At least once per 31 days on.a..SAG. . %Q -RBASJ.by iniatt:

410 q4- 4: 7ad (A b 1 -At af,-verifying

-4e*zton...p.r.18 that the syst . pa rncnj.. .""

. -... yfoa rE t 15 minutes.

e..r'a4es See insert markup of SR 4.7.6.1.2.b -;; the and c.

tn'snno.. rn. ,^ ".

adatia-tst t ignl e heractua or smulatedudthe

-l system auomatoical isolates theDcontrol roomwi c!.4c-f.e .r.prsea14eU;.swichsinorcamreciculation Al

_c.....t* e4fo-m+na ,h, re5red Conhutrol t tooernth!......ncmtcnY

2. 0504e'Of 44Ventoatso..e0filte testing4 in accordance.wth the Ven~ation FtlterT.esting.P-ooram ,(VF'Ti:*} NL ARKANSAS - UNIT 2 3/4 7-18 Amendment No. 494,206,24.,

Next Page is 3/4 7-22

SURVElLLI.NCE REQUIREMENTS (continuod)j

d. At least c*n*

pF 18Gneths-ID,ý

1. Verifying that the pessure drop acrss the combined HEPA filtero anld charcoal adsorber bnk i - 6 inche..Watr Gauge while operating the system at a flow Fate of 2000 cfm 1%

2. Verifying that on a control room high radi-atioan t~~n the -ystem d.1, e. and f. automatically isolates the control rOOM Within anM4 switches.

-Ia-Condc will be into a recirculation mode of operation With $1 the HEPA filters

-reuh relocated to and charcoal adsorber: banks.

the VFTP, proposed TS o.Afer eah comlete oF partial replacoer -E A it&n b14r~'

6.5.11, with that the EAfle banks rcmo~: :9~~of the DOP wilTe rctse minor inplace ;n c nce with AN .igemat a changes flow rate of 2000 cm+/-1%

noted. See markup of f. After eacah completc Or partial relemý~~rols rberbank by insert. v.erifying that the GharcoaIl~rbr-- rherns ~ 9.5 of aXalgn hydrocarbo r-rgrn te ,s .r. whe the:

.t.d.in place in accor~dancGe d.2 will be with AdS N5017 hleo--test~ lwrte of 2000cm moved to new I S% e - h l g

,, . .: .I ...

4.7.6.1.2.b A~ "

Sj ARKANSAS - UNIT 2 3/4 7-19 Amendment No. 2--l,

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

If any snubber selected for functional testing either fails to activate or fails to move, i.e., frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be evaluated in a manner to ensure their OPERABILITY. This requirement shall be independent of the requirements stated in Specification 4.7.8.d for snubbers not meeting the functional test acceptance criteria.

g. Preservice Testing of Repaired, ReDlacement and Snubbers Preservice operability testing shall be perfo 9n!r.A aired, replacement or new snubbers prior to installation. Testing may tthe aurers facility. The testing shall verify the functional test accept. nce criterir .78.e.

In addition, a preservice inspection 1eperoed on . aired, replacement or new snubber and. "T verify that'

1) There are no visible signs of dr "paired operability as a result of storage, handlin nallation**

2) The snubber I.ocation >entation, position setting and configuration (atto.b s *.,, are in accordance with design; lk '

3) A0 a te Swd cleara provided t allow snubber movement;

4) M..pplicable,

. is at the ommended level and fluid is not leaking from S........onnections such as pins, bearings, studs, fasteners and other tchi, e Urdware such as lock nuts, tabs, wire, and cotter pins are

h. Q-. Snubber Sear1place ent Program

&eal

. servj. *4e of hydraulic snubbers shall be monitored to ensure that the serv.,. life&&..."It exceeded between surveillance inspections. The expected servi*tf@$ he various seals, seal materials, and applications shall be determi and established based on engineering information and the seals shall be replaced so that the expected service life will not be exceeded during a period when the snubber is required to be OPERABLE. The seal replacement shall be docum e nt d -.* ., ..r'e .... . -,l .*.. ai . .e it ARKANSAS - UNIT 2 3/4 7-23b Amendment No. C2-,

PLANT SYSTEMS 3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.7.12 The structural integrity of the spent fuel pool shall be maintained in accordance with Specification 4.7.12.

APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel pool.

ACTION:

a. With the structural integrity of the spent fuel pool not i ng to the above requirements, in lieu of any other report, prepare a bz-m ecial Report to he

.* , t ,.t withiin s of a determination of such non-conformity.

b. The provisions of Specification 3.0.3 are. " pplicable.

SURVEILLANCE REQUIREMENTS 4.7.12.1 Insection Frequencies a intdg.f tural the spent fuel pool shall be determined per the accepta." -"k*!k aof Specliowtion 4.7.12.2 at the following frequencies: 4

> :.,v * ' S*'

a. At lea MWper 92 da po ted with water. If no ab ei due abnc""'i'*'@'dedr- 1?p. io norsb~

tion e eofs indications of structural distress are ted du` ng*e consed1e inspections, the inspection interval may mb~xended tQ~n east OF= ..* .. ocAr5 yas N Withiffoao

%i&Ye a~ igtd the seismic I~smic instrumentation.

nitoring event which actuates or should 4.7.12>" Aceptan; ria structural integrity of the spent fuel pool shall be

"'d d te ined Ok sual ction of at least the interior and exterior surfaces of IAe poolhe e st nithe ilt pit, the surfaces of the separation walls, and the

ttural slabs adjoining the pool walls. This visual inspection shall verify no 2 or other signs c*-s in in'gth'. crete crack patterns, no abnormal degradaton the. rdainorohr in of st bal ts (i.e, cracks, bulges, out of plumbness, leakage, disco~l " efflorescence, etc.).

ARKANSAS - UNIT 2 3/4 7-38 Amendment No. 4,1-41-7,4-194-,

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. Two physically independent circuits between the offsite transmission network and the onsite Class 1E distribution system and

b. Two separate and independent diesel generators eAth:

1. A day fuel tank containing a minimum W i,280 gallons of fuel (equivalent to 50% of indicated tank v'e), %

2. A separate fuel storage syster ninga minim lume of 22,500 gallons of fuel (equiva..ntc* 100% of indicated level),

and

3. A separate fuel transfer pump.

APPLICABILITY: MODES 1,2,3 and ACTION:

a. With one offsite A.C tgf the a eet power sources inoperable, perfQ :ie...f61: I"" g:.

1. Dem t the 0 BILI remaining offsite A.C. circuit by perfor p ReqreW V. t.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least

pn,.per 8 V 2; " testo s is,*,-A .C. circuit to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be

" in at leastf~T iA .BY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD

,*...SHUTthin ,lowing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Startup Transformer No. 2 be remov, fro M I for up to 30 days as part of a preplanned

%3preventative n tenance schedule. The 30-day allowance may be Moved actiion b p notm 'han once in a 10-year period. The provisions of and Note 1 to new So"' catior114 are not applicable to Startup Transformer No. 2 during page 3/4 8-Ia. the :f ypventative maintenance period.

urzinepzrzable, pe-t-hom., the follew:1ri: Al

!,Pezneas~trate the OrERiABIL;TY ef beth the. effaite A.G. e!Eeults by perfzrrning Sw. .5J.J.1anee. Requirzrnet 4.s... w:itahjn :I heur and ait leasit enee pzer 8 hezurz therzzifteE, and

2. Pemens.trate th: OrPEWAEIL;T-Y ef the *ernairlirg OPEPABLE; diese gzxnzrate. by perferminq Sutvel11..rez fealzciuirerazi A fl I I -

... w...h. .... 24;;..' n'ur-9 zn..... w z-.

1. A axaen eause fallur,. hq hp r-.l ARKANSAS - UNIT 2 3/4 8-1 Amendment No. 444,24-5,234,

(5) e

)5 44 S (

4/

r z

r

4 Sc A

E

'a

$1 110-11m p.'g ED 4,

alOW PA"'rA C')

AM I.

Ir 1 .4 SI 54 I' 2t E S.

144 4r CN I

SC i I~

fl%

MR44 z

IC I'

IC C0 pv Ia z

4

.5 11

ELECTRICAL POWER SYSTEMS A.C. Sources LIMITING CONDITION FOR OPERATION (Continued)

b. With one diesel generator of the above required A.C. electrical power source inoperable, perform the following:

1. Demonstrate the OPERABILITY of both the offsite A.C. circuits by performing Surveillance Requirement 4.8.1.1. 1.a withirk1 hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, and V<

2. Demonstrate the OPERABILITY of the remain.Z" RABLE diesel generator by performing Surveillance Requirfmt 4. .2.a.4 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months except when:

i.

ii. AThecommon remaininglt~cause failure has bee, .ermined not to exii'.

diesel ,qeeneratdý'.'-.4ý'Abrrently ilnoperationo iii. The remaining dieseldieneratls been din strated OLE within the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and'*-; .'

3. Restore the diesel gen.tO-.-, OPERABL.tatus within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (See note 1) or be in at least OT**-TANDBY withfi1e next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN withinhe f6lfp.30 hou.....

Note I - The requiremen ta eselgenera.r.O ) restcn to OPERABLE status may be exteradto e16fdaysif thAternate AC dibsel generator (AACDG) is verified av, lile. If the-AMCDG is ond unavailable during this period, the 72 hourf ie

ration eri..6obf conditi6Wb.3 is immediately applicable until either the AADG or.hetO -Js returft'W to operable status (not to exceed ten-days fromifu:ii.tJi* ii*"atoY inoperability). The 10-day allowance

.blpled ) onj'bnce for eaclEDG.

Al

%0-1~

ARKANSAS - UNIT 2 3/4 8-1a Amendment No.

ELECTRICAL POWER SYSTEMS A.C. Sources LIMITING CONDITION FOR OPERATION (Continued)

.A.T!OGN ,(Gntlnwed)

c. With one offsite A.C. circuit and one diesel generator of the above required A.C.

electrical power sources inoperable, perform the following:

1. Demonstrate the OPERABILITY of the remaining offsite A.A uit by performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at -once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, and,

2. If the diesel generator became inoperable due to a use r than preplanned preventive maintenance or testing, *

i. Demonstrate the OPERABILITY of maining OPERAB sel generator by performing Surveill equireme.pt 4.8.1.1.2.a. in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months except when:

a. The remaining dies*.eenerator is i*tI in operation, or

b. The remaining died rator has );.emonstrated OPERABLE within the previous i

3. Restore at least one of the inoper so t R status within 12~ ~ ~ horsorbein01OTS

~ su* n' ,i 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in a n 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN w ef .ing 30d

4. Restore bot~ffstcircuits "4h both di crgenerators to OPERABLE status within 72 hou(rM eb 3.i-f the init, iing event or be in at least HOT STANn oxrs6in ,LD SHUTDOWN within the following

d. WiAftl io offsite A.t(fuits v above required A.C. electrical power sources inopetable, perform thi' "lowi&

1. Pe it6w Surveillance*quirement 4.8.1.1.2.a.4 on the diesel generators within the nekt<O ours exs '*Vwhen:

i. The diew Q1.' ators are currently in operation, or ii. The diesel.inerators have been demonstrated OPERABLE within the previous 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and

2. Restore one of the inoperable offsite A.C. circuits to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , and

3. Restore both A.C. circuits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the initiating event or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

o.Wrth two diesel generators of the above required A.G. electri3! power sourcec inoperabl*, perform the following.

ARKANSAS - UNIT 2 314 8-2 Amendmonf Nn AAAI-'VA

1. Demonstrate the OPER-ABLITY Ml of the t.ýo offsite A C. circuits by pGerMing Sur~i!InceRequremnt4.8.1.1.1.a A':ithin I hour-I and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Al

2. Restore one of the inoperable dicese gneRentors to OPERABLE status with~in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in a least HOT ST.ANDBY within the nRxt 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , and

32. Restora both diesel generators Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (see b.3, Note 1) of the iiitn eveont or be !inat least HOT STANDBY Within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months a insCOD wie ll be moved to page ,+

44.

-~

V ++.I: -.+

ARKANSAS-UNIT2 3.N

\ %

ARASS- UNIT 2+." 3/ -2Aedmn N"441 3

. . .. . . . . . . . I i v " S..

ELECTRICAL POWER SYSTEMS 6SURVElILANICE REQUIREMENTS A A.C. Sources LIMITING CONDITION FOR OPERATION (Continued)

e. With two diesel generators of the above required A.C. electrical power sources inoperable, perform the following:

1. Demonstrate the OPERABILITY of the two offsiot, A.C. circuits by performing Surveillance Requirement 4.8.1.1.1.a witIfbiff hour and at least Al once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, and

'2. Restore one of the inoperable diesel genera B BLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in a least HOT STANOB'?within tit.kxt 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the folloZ i90 hours, andY= .

3. Restore both diesel generators wit. 412 hours0.00477 days 0.114 hours 6.812169e-4 weeks 1.56766e-4 months (see b.3. Note '*kth e initiating event or be in at least HMT.ANDBYhin the next 6 Ws and in COLD SHUTDOWN within the fo~lowi*r hours.

f. With the volume of the separatl .storaoe svst _. utside the limits of action f.1 or the Al new or stored fuel oil properties" ,si

e limits of thDiesel Fuel Oil Testing Program, perform the following as approprit:, (N!te*2". '

1. If one or moweworage Skit's cs 22,500 gallons and greater L4 than 17. 44V t*"hestore th il volumr within limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

2. Ifthe 411 ed fuel oil t articul are not within limits for one or more diesel L5 nenerat store4i9..oiLftotal pa~u- lates to within limits within 7 days.

3. e

loNt, 1 berties are norWIh in limits for one or more diesel generators.

STrestired oil properties to within limits within 30 days. M6 M, If action f.1, m*t.thin

-t the allowable outage time or is outside the

... *allowable lim .sorif adtbn f.2 or f.3 is not met within the allowable outage

\_.me then imniydiately declare the associated diesel generator inoperable an ,erform thk'Mppropriate action.

Note 2 Separat n. i0. entry is allowed for each diesel generator.

14- ach of the above rogUircd independent circGuits between the rm11 A or-%t.O. 1. 1. I

& 4.8.1.1.2 and associated a. Determined OPERABLE at leastonca per 7 days by Yerifyinq correct notes will be brzakcr alignrnents, indicated power aVailabilit', and moved to a new page b -Demonstrated OPERAPLE at least once per 18 months during 3/4 8-2b. shutdown by transfwrring (manually and automatically) unit power supply from the noRmnal critto-the alternate ci1rcuit ARKANSAS - UNIT 2 3/4 8-2a Amendment No. 444-,237,

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ELECTRiCAL. POWER SYSTEMS Q A.C. SOURCES SUR VEIL LANCOE REQUIR EE INT, 4.8.1.1.1 Each of the above reouired independent circuits between the offsite Al transmission netvork and the onsite Class 1E distribution system shall be:

.. a...... Determined OPERABLE at least once per 7 days by verfy. correc b.eaker alignments, indicated power availabilityw.and

b. Demonstrated OPERABLE at leant once Ofrmonths during shutdown by transferrino (manually and*MatcalMy} unit power suoply from the normal circuit to the R uit.

4i..*1.2 Each diesel g.eneratorshall be demon OPERABeo.-u : Al 4..-, a ......

h.d,je .!,.se t.o.

q? , *,er.3...**

.. -t em-.)

. ...........:- -2..T ........... nil... ,

.. 2I~

At meast once pe 31dyG

a. .......... . p

.Yb0.y.. ~A GERED T........

1. Verifying the fuel the da, a.:V aq tank.

2. Vefifving the fuellevel it storace tank.

Vn ...

transfers t 'rd some I. .n) to the day tank.

i!to the ef s:' a........g.orovijdest.andby S * " p T.b- S s , o.nd . .........

- ven ýthe- . btinojr is svncc.rized, loaded to an indicated 20 5Kw o~ptwerates for'C0 minutes. Vtes 3fu4) rire.ed.dby reub bussesr

..... ....... ...d .....

e.

M#

oil~~~e of--new-andrstore -~L feoil are tesed in aoridesance;ý M-7,*

- on Ge... tot Verlfv fuel "Nt orl rDes, of new and plieed sdoringmaybeacin are d in avdordance thet r 1Lare aiowained withio n the limits ofa the Diesel Fel Oilenestinr I 2/42robAmendm..

-U .....

a...e ..... .o ~

aybein...ccrdnc sureilace ...............................

w v th u.r~ nedor..... s..oft.~.s.

recommedatnions. ASM L rp s ................. il ....

n.uv e ......

preceded by prelube, proredures.

Note 2 T his diesel -generator sta.rt fror. a standby, .ondition in s, 15 sec. shall be A accmplished -atleast once even, 184 days. All other diesel gnrtrsat o ~i sunieflia.nce may be in accordance with vendor recom-mendations.

Note 3 Di.esel .generao lo!)ng mAleacmp*hdi ccrac recomnmenga.tions su%^.h as *rad ual loading.,

Note 4. Momentary trans~ents outside this load band due to chanrn*°"ioas c " not inv=,alidate_,:"- f

'he test. Load ranoes are ailowed to preclude over.- loadino t~he diesel oenerators.

A-*KI¢NbAb - UNI 12 3/4 8-2b Amendment No.

ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. One circuit between the offsite transmission network and the onsite Class 1E distribution system, and

b. One diesel generator with: ..

1. A day fuel tank containing a minimum ne 280 gallons of fuel (equivalent to 50% of total tank voluj

2. A fuel storage system contain'.. inimum volunrt2,500 gallons of fuel (equivalent to 100% tank volume), an*

3. A fuel transfer pump. Io X, APPLICABILITY: MODES 5 and 6.

ACTION: "%7 "a. With less than the above minimum id ri ewers sB suspend operati-opllIyng

.*viC sA1tTY ar positive reactivity changes.

b. With the volumAf e fuel age sys* outside the limits of action b. I or the new or Al stored fuel oflý operties outAe the limitleSSthe Diesel Fuel Oil Testing Program, perform the foli a asa.t....'..'.

1 L* 61. ,guire

'0s"el generatol ahd greater than 17, ciated fuel storage tank contains less than 446 gallons, restore the fuel oil volume to within linLrt ,._,thinU

.. ,..Stoe il tot mitcua aen 2 .' I:f thestored oI tot artculates are not within limits for the required diesel

"*enerator. resb fuel oil total Particulates to within limits within 7 days.

3. Iffn elorW*1perties are not within limits for the one required diesel

'engftostore stored fuel oil Properties to within limits within 30 days. M6

4. If action b.1 is not met within the allowable outage time or is outside the allowable limits, or if action b.2 or b.3 is not met within the allowable A10 outage time, then immediately declare the associated diesel generator inoperable and suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE REQUIREMENT 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1 and 4.8.1.1.2 except for Requirement 4.8.1.1.2a.5.

ARKANSAS - UNIT 2 3/4 8-5 Amendment No. 449,

REFUELING OPERATIONS FUEL HANDLING AREA VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.11 The fuel handling area ventilation system shall be operating and discharging through the HEPA filters and charcoal adsorbers.

APPLICABILITY:

Whenever irradiated fuel is being moved in the storage poolptutrng crane operation with loads over the storage pool.

ACTION:

a. With the fuel handling area ventilation syste/4%operating, suspe' 11operations involving movement of fuel within the sper4f44l pool or crane operatil~ith loads over the spent fuel pool until the fuel handlin ga ventilati {.ystem is restoAMo operation.

b. The provisions of Specifications 3.0.3 are not SURVEILLANCE REQUIR 't4*kd' Ký 4.9.11.1 The fuel hin 41 .9 ling u-*'..

garea h the ý..*..RA. s ep!ation shall be determined to be in operation and dPschargters a harcoal adsorbers at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .IVN

,*.u.*1.2 opde"i*ing Ar,,ventilation AA system shall be demonstrated OPERABLE 4h A irradiated fuel is in the storage pool by,D*eforming the

.* '*a.q.j..Jred

~ ~.......

....X6

..... A

...... ... .-q 4- ** . . 'tinin .. accordance with the g Ventilation P . . Testjng Filter .......

i *y'10zonc communRcatInci with the cvztom by:

See markup of inserts for changes.

ARKANSAS - UNIT 2 3/4 9-12 Amendment No. 434, Next Page is 3/4 9-14

StRVE4LIANGEF .RF:Q4RE.MEN4T-4Co4inue

2. Voifyings within 31 days tare removal that laborator nayie rspsctatvaeatn ample Obta'ne inacranca with Reguiaty Poste zgbtoy C..bofuid 152,Ro~ia 2 Mach187,shews thedieeta~p yki ne w lio ~ e s~ h n.$ 0 %w he - tes G1 n ao o d r e of-9WY

3. Var-lying a!syIc4oM flow r *g Syte k atart. 7)A ka. en, aS dayf aftefenaa taa.a1otte#iks itEtidyvl4l.ybpyl1f4n+.4H.

Gu4.52, Revision 2: Mat~h At~.e-en.

. P than 50.0% When tas-ted in iazeo~rdeoAAWDOC-S3wt

-- '~ ~r~' .r~'94 .Iaflrr-at!

c bn.. P P ite.& . ... n...

... I n e....s1.. ter...

-YU3 of te DOPwhe theyd-r-k ai&Gotedi

~~~~~~ 0i-noesin7Te-yerAt4^i See markup Of v inserts for changes. $

.A.R.K.-A..h.1 AS UNPI-2 3/49-13 ARKASAS NIT3/49-13Amendment No. 228,

ADMINISTRATIVE CONTROL6.,

RESPONSIBILITY A13 6.1 6.1.1 The A4Q-2-.pPlant rf;.anager ANO".-Oeratiorns shall be responsible for overall unit operations and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 An individual with an active Senior Reactor Operator (SRO) license shall be designated as responsible for the control room command function while the unit is in MODE 1, 2, 3, /

or 4. With the unit not in MODE 1, 2, 3, or 4, an individual wvt,an active SRO ¢e-sor CAl Reactor Operator license shall be designated as responsi** the control room command function.

6.2 ORGANIZATION 6.2.1 ONS....E AND OFFSITE AN.. S4T-ORGA be T. IONS ope4i ad orort Onsite and offsite organizations shall b blished for unit and corporate management, respectively. The onsit d offsite Fganizations include the positions for activities affecting the safety .... nuclesd".dwer unt.Al

a. Lines of authority, responsibility, and co '_Wlcation shall be defined and established a " thrQhou. '-hest management levels., thFre,,h' intermediate levels, all oper "igorganization positions. These

-4,a Al relationships shall be docnl t ,appropriate, In e..fr-of organization charts, functio .esc8 dep'mental responsibilities and relations hipu rJb de s y pel positions, or in equivalent forms of odumentat*:* . Thse irements., cluding the unit specific titles of those p nel fulfi 4*hru- onsibilities of the positions delineated in these Al Techi pecificati * ..*: e'

shall ented in the Safety Analysis Report A3(SAR) .* *

'-*b'.'# egg 2i*e

nagionsshall be responsible for overall .ýf*t v'-' v [tio ry h"e unit -' and shall have control over those onsite activities F4.>"' necess"t.y3f, sa'*f ,eration and maintenance of the unit:.

-an

" specified rate ecutive shall have corporate responsibility for overall

.'*ar.*t..-Jn nLIf =rsafety and shall take any measures needed to ensure Al ptable p mance of the staff in operating, maintaining, and providing te::nicaI su j to the .lAr4-unit to ensure nuclear safety. The specified corprte" tive shall be documented in the SART.A1nd Al rill be to d. -2 ofin' :

The uals who q rtrain the operating staff., ....nd those ............

whcarry rt ... out health oth healthi A

-2 of physics.-ar*P4-or p~Ž.~~...e...quality assurance functions may report to the appropriate Al an onsite manager; however, thesýgy.-ndiv.iduals shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 UNIT STAFF

a. Ea-ch o dut, ch* shall be cerpsed of at kass the minim, hit ctrw ccnoio h~i al when fuel s in the reactor and two .additional ~non-licensed operator shaiD be opn site non-licensed operators shall be on site when the reactor is in MODES 2 3.3,. or 4. n.... ............. p. --.--

" s--a..-. b.e.--.--.--

A, ,S,,S -UNIT-2 6-1 Amendment No.

209II

b Atoctoecns-Oratar sha!I b-104eGnr! omwhnfo ic in the reao1m;h minmm shift crew corn osto o licensed operators shall meet the-al minimum Stffiiqg reairments of t~CFR 50.54g(2Qfoon rLoecntl room.g ir ARK-ANSAS --UNIT 2 6-1 Amendment No.

,52,57,73,85,87,98,444, 19, 209-,

c. At least two !iconsed_ Qocrators shallbepsntithcnroromdin Al FeaotoeT-str uohtdrotosudn and drn eoeyfo

eao.o..rips: Shif. crew ceomposition may be less than the minimum reQuirement of 10 CFR 50.54(m)(2)(i) for one qnit, one control room, and 6.22.a a:,' 6 for a neriod of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommoate '-unexpected absence of on -.duty shift crew members

.proviedimmediate action is taken to restore the shift crew composition to within.the minimum. requirements.

d. An individual qualified in radiation protection proceduj4.hall be on site when fuel is in the reactor. The position may be v# or not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for Unexpected abse fl vided immediate

?~ction is taken to fill the required position.

'*~~~ '""* *"*t_ "*" * ..

.. ~~..........

t O A supor for th hechica advisoryq O In MODES 1, 2, 3, or 4, an individual 11 e advisory technical support for the u.i.operaUons shift sup*rew in the areas of thermal hydraulics, reactor engi$#t tg. and plant ,i:tIysis with regard to the safe operation of the unit. Thl nij; me!Vthe WUshalI qualifications specified by the Commission Policy ter..

....... .gin ngin Expertise on SShift. A e.. .e amount of overtime worked by.*4tirfitaff mem#?erforming safety-related functions r

...... s. W[Pe limitedlm.. and controlled in accordance with $C Policy Statement on working hours (Gener ""A N FI. sO, ratio .ger or the assistant operations manager shall hold a sef)" i2S*'.RO license. l

.,R..S,,S U.NT4 6-2 Amendment No. 47,25,2-,2,73,65, 8:7,98,411,132,209

U 7

'2 7

3 40>

f

( i-1)

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(0

.1

)

d9

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS M7 6.3.1 Each member of the unit staff sh meet or exceed the minimum qualifications of ANSI N18.44...ANS 3.1- 78 for comparable positions, except for (,--)the designated radiation protection manager, who shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, September 1975.

CTS 6.14 6.4 DT ýPROCEDURES Subsections are later in markup.

will be relocated **:

hereosed here-see 6.5 PROGRAMS markup ."' ..

later. [6.5.1 thrugh 6.5.6 will be used latcer.) Insert 2) 6.5.1 Off.ste Dose Calculation Manuam (0DCM)

".5.2 Primary Coolant Sources Outside Containmenf Vt 6.5.3 not used CTS 6.8.4.b will be relocated here CTS 6.8.4.a will .4 Radioactive Effluent Controls Program see markup later.

be .5.5 Component Cyclic or Transient Limit Proo Meii relocated here - see 6.5.6 not used . A markup 6.5.7 Reactor Coolant Pump Flywhee.nspection Pr later.

This program shall provide for &inppg*n of eaor coolant pump flywheel per the recommendation of Regulato osiU A of I atory Guide 1.14, Revision 1, August 1975. The vplumetric e *inatrl pg ry Position C.4.b.1 will be performed on appr Mg O-yea 6.5.8 Inservice Tes .t..ogram >

This program ds jnsertesting of ASME Code Class 1, 2, and 3 compojents. Th*1

hi* eth following:

Iha New Pages esng ..er *,eclfied in Section XI of the ASME Boiler and Pressure will be added "-"Vessel Coa'&txl:*t 'ai ble Addenda as follows:

as needed. A

/ j SME Boiler tf'ressi*.i.,Vessel

"\ .dean ap le Addenda Required frequencies nology firvice testing for performing inservice adcii*.es testing activities Weekl At least once per 7 days Monthl At least once per 31 days Every 6 weeks At least once per 42 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice testing activities.

c. The provisions of Specification 4.0.3 are applicable to inservice testing activities, and ARK-A..SAS UNIT 2 6-5 Amendment No. 6, 12,17, 20, 20,52, (Ne~d page ispage 6 42a 7;, 85,98 114, , 11, 47, 416*,

20n,233

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

6.5.9 Steam Generator (SG) Tube Surveillance Program Insert 3 IInsert 1) b. 1 SecondaryWater Chemistry 6.5.11 Ventilation Filter Testing Program (VFTP) A I-et 6.5.12 later . _Insert 4) Ir *)

6.5.13 Diesel Fuel Oil Testing Program TS Bases Control Program Ison page G 6.5.14 Technical Specifications (TS) Bases Control Progrm 12a. a 6.5.15 not used CTS 6.15 will be relocated here - see markup later

.ARK.121-41SA U IS 1T-2 6-5 Amendment No. 6,42,17, 20, 29, 52, (Ne" pageIpage6 42a 73, 5,98,11 1, 11132,1 4.7,60, 29,n233

Administrative Controls 6.5.14 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without priory approval provided the changes do not require either of the fop g:

1. A change in the TS incorporated in the lice *,,

2. A change to the updated SAR or Ba at requir e .Capproval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall 40 din provisiQWn to ensure t Bases are maintained consistent wit!SAR

d. Proposed changes that d reviewedee ot m Iabove e f 6.5.14b 4broeabove shall be*

be reviewed and approved C prior to' pementation. Changes to the Bases implemented VMOutN R ap !Jshall be provided to the NRC on a frequency c CFR 1(e)

W.,

A.R.K.,NSAS UNIT-2 6-12a Amendment No. 4 4 7 46 0

, ,2 90

ADMINISTRATIVE CONTROLS 6*.*

'.:...L.I~ T.V .. (A14\

A take;;,fet t-7 Limit i ~l~d . i.h.,n.-24, All 6.44.. PROCEDURES-A.N*.P:-tRP-.SM2 $ * .*.% Al R C 6.46.1 Written procedures shall be established, implemp...d' ad ma,14ted covering the followinga activities:44-ee*

a. a-The applicable procedures reco Guide 1.33, Revision 2, Appendix

....ded in 2!!

oci Al bruary4t_

b. The emer!enc operating MŽWedures Frea.i the reguirernents of NUREd N*IR M -t 1,as stated in S ,ction 7.1,.., ....

......... .................. , .. . ... ... of.8. ....

f. Fire o Pr impleme nA-l

d. 6.5. and Modifi a o -.0 protection c~alculator (CPC) gA.ddressable "r...thonatan so...tedures provisions to a-sL dho-l-shall.include e...s...r..

.. I Jnt in is maintained in CPC 4Ttype I addressable onstts to exessive operator interaction with the CPCs during

ý.eqqctor operatri NM ..od ions to the CPC software (including changes of Al algo f*iuel cycle specific data) shall be performed in accorda{ with the most recent version of "CPC Protection Algorithm Software Change Procedure," CEN-39(A)-P wl-ich t*at Al has been determined to be applicable to the facility. Additions or deletions to CPC addressable constants or changes to addressable constant software limit values shall not be implemented without prior NRC approval.

64 . ý,-W'ets.f.fl

....-- ... lN i.t*,.**.

ARKA.NSAS UNIT-2 6-13 Am-ndment 1o.

21,i8I13,52,6O63.V3.l7I8Vl *i 9 I0iI 8l

ADMINISTRATIVE CONTROLS 0

6.5 Programs and Manuals

"*A-The following programs shall be established, implemented, and maintained-..

---.-.-.......-.. 65.4 Radioactive Effluent Controls Program This program conforms with 10 CFR 50.36a J&0the control of radioactive effluents and for maintaining the doses t"Bi MBERS OF THE PUBLIC from radioactive effluents as low as reas*ibI"y achievable. The program shall be contained in the ODCM, shal ented by procedures, and shall include remedial actions to bt wýher the program limits are exceeded. The program shall in e the followi.. nts:

.e follc emens 4--,. Limitations on the functional capa t radioactive liquid a6'41seous monitoring instrumentation includi*'rveillance..sts and setjtetermination in accordance with the methodology tpe Oe 0

"2.),. Limitations on the conce.fa,tions of radib:ti e material released in liquid effluents to UNRESTRlMA. -EASc . '" ,g to 10 CFR Part 20, Appendix B, Table II, Column 2;

)c Monitoring, sa,.plig, and aq . Ye i*'d and gaseous effluents in accordance i R 20. 2& ith h thodology and parameters in the ODC21'ý " i SLimita~ on the an Itand qua 'y doses or dose commitment to a MEMBER OF THE" LC f a. .e ierials in liquid effluents released from each mE":t: Nk -fiormingto 10 CFR 50, Appendix I; effluents Dt o..-Wo-4-dose e contributions from radioactive

..- efflent f cu :.calendar quarter and current calendar year in accordance

"* with the me ogyrc$ parameters in the ODCM at least every 31 daysj1

% letfrrnabi*

or ... e6d dose...ntrfu..ons fmradioa.*.ye efflen.s, in rdace he rethodologyin the DCM. at least every 31 days.

g. U

functional capability and use of the liquid and gaseous effluent "t- ate: ms to ensure that appropriate portions of these systems are used t redu leases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table II, Column 1; ARKANSAS - UNIT 2 6-14 Amendment No.

5,52,73,85,91,98,4 14,119,147,160,193

,25,209

ADMINISTRATIVE CONTROLS

- Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; C W'iL Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days In gaseous effluents released from each unit to areas beyond the site boundary,.* rming to 10 CFR 50, Appendix I; and

... Limitations on the annual dose or dosel .ent to any MEMBER OF THE PUBLIC beyond the site bound. ue t ses of radioactivity and to radiation from uranium fuR[cle source forming to 40 CFR 190.

T-he

......provisions

............. ....of SR 4.0.

................ dSR. 4.01"eap

....." a... . ..fcbe ....... Radioaotive...

. ........... ..... ................ c...

Component Cyclido rTransient Lf

............. 6...............

5:

6.5.5 4 r,. Al This program provides*cthe . Section 5.2.1.5. cyclic er-and Thinsieprogcraprovides to e*.#e 1 r+ck th**+

.--,6 transient limits.

REPOR-occurrences

to

. ea

'EMENT*

ti c" -11* n'.*l**it maintained within the design CI AD MIX.T. h 4 e4Aaltka;

.I..

r4 W.04,i.4a A Cr*.-.a iV at4.+ . ... . .

. . .: S..*- .,>**.;..** *, .a* .

"" PJA-montal-y -rapW46. .04A -9ý4-W-!ýRW ý4 44 SSA -WWV -4 4r-a e -rAC441 S. -UA41-a' ý#W" -ev-0 ýrw -4 ave -b 4" cQmiI4'0Mfo ARKANSAS- UNIT.: 6-14a Amendment-No-.

6,52,73,85,91,98,111,11149,147,1460,4193, 205

ADMINISTRATIVE CONTROLS

,A17

(%9rt44r.h14tO.ft, e.. , ,

6.6.1 Occupational Radiation Exposure Report (Note: A single submittal may be made for ANO. The submittal should combine sections common to b.ot a.. .A tabulation on an annual basis fwot-.of the numb@1tdf",tation, utility. and other If personnel (including contractors), for whom monitorid ft.. om.ed. receiving an annual deep dose greatert,.W$OO. mrb-pks iX&U~e5.O~uiVaient and their.

associated collective deep dose equivalent (repd in roe-song .. em'. eewe according to work and job functionsA (e.g., re operations an eillance, inservice inspection, routine maintenancea..,,,l',*:..:-*, maintenance (des .

maintenance), waste processing, and reftjllffg,. Thist-bilation tlihe regu'rements of 10CFR 20.2206. The do ssignm**,Ao various dutyfehions may be estimatesd based on pocket hemoluminesence

.on.zatast1tKa A18 dosimeter-,-rTLD),electronic dos er. or film blidrmeasurements. Small exposures totaling less than 2 11 ismt of the i ual total dose need not be accounted for. Inthe aggregate,' rft 4 e total who!e.bo4ydeeo dose eAuivalent received from ext 0 1ors 4al to specific major work functions. ;repor c sin y sshal be su mte ,A r--0 .. . year. L9 o...............K;.. m~e~~rIybe. 1%P2.;:;{' .illance Re '* -te-*

Tee-peeett t fn..........

P, Une* .. vc V soe tHhi0 of steam ,eneator tubes, the numbefr oftbes plu'PI P e

e.n..e.r ...o........................r#

.. g~cYrator shell be renortedj ... . ........... o w.hi

. i............. ..........

AM:ýý

.?N ' tot-umision within 15 N1 ...

and extent of tubes insoected.

2. Location and pereent of wall-thickness penetration for each indication of an imoerfection.

3.;... id,.,entifato .. of tubes plu.

c. Resulis of steam generator tube inspections, %which fall into Categlofy C-3. shall be reportedikna Special Repot pursuant to Specification4 .9.2 to the Co.mission as denoted by Table 44-2.-5. 9-2. Notification of the Commission wil1 be made nor to osmoion... ,'. *.mof£

.t..o..m . .tLo.pl"hant.

.n. .o~..p!.a.&o*peration .a.....e.*£~.t..*...n*9...th..n.Mode.

t.. .*. .r t.o....n

... .b .P..d.... ......t......e. .t.e...n...*£ Tb.g.s..#o....£t..t

.. .#g.......... ..........

Zb ...*.'...e.........

A,RKAN*.SAS UNIT-2 26-15 Amendment N. 5,11,91,92,237

determine the cause of the tube degradation and the corrective measures taken to orevent recurrence.

0......... . ......r *£ ,'.e~ e.

&,tP4l 4)o. (

............. 6.6.8 The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months pr to the first sample in which the limit was exceeded; (2) Results of thej4S*.?4topic analysis for radioiodine performed prior to exceeding the limjte$lts of analysis while limit was exceeded the results of one analysi .radioiodineactivity was reduced to less than limit. Each result S Rld ene date and time of sampling and the radioiodine concentrae Cleantsstem

,,;3)Y flow history A...... ;..a. hebe*shd. 81 Al N~. CRP.~M ARK.I",.SAS UNIT-2 ARKNSA UNT 26-15 Amendment No.5,41,94,92,23:7

ADMINISTRATIVE CONTROLS starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.

6.6.4 MONTHLY OPERATING REPORTS A kl 4.4t.-Routine reports of operating statistics ann shutdown exp e shall be submitted on a monthly basis no later than the 15th of each month following 01endar month covered by the report. wihi*h*A fjT. f.he-104~ -e Pi~ 4acO SASee individual soecifications.

ARKA*NSAS UNIT 2 6-16 Am.ondment No.

.4.....:......... eG. t d6atiGRMGni4O!E See individual specifications for i.,

.'t-0-.Reý j., k., n., and o.

&,Socfir.tio I*A c. ,. ---. A

-. ........... te (Al ARKANSAS UNIT 2 6-17 Amendment No.

60,63,.,123,. 15,157,1p3

ADMINISTRATIVE CONTROLS Ql 6.6.3 RADIOACTIVE EFFLUENT RELEASE REPORT

.-*The Radioactive Effluent Release Report covering the operation of the unit in he Previous year shall be submitted prior to May I of each year in accordance with 10 CFR 50.11a.

Ki The report shall include a summary of the quantities of radioactive liquid and gaseous efflue ts and solid waste released from the unit. The material provided shall be consistent with :he objectives outlined in the ODCM and Process Control Program and in conform ce with 10 C 7R 50.36a and 10 CFR 50, Appendix I, Section IV.B.1. A21

-*2!-Not. A single submittal may be made for ANO. The submittal shIall ine thae sections that are common to both units. The submittal shall releases of radioactiv

.4.he material from each unit..

Move note up on this PiHne.

ARtNSAS UNIT-2 6-18 Amendment No. 60,914120,157,493

0 ADMINISTRATIVE CONTROL 6.6.2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.94-The Annual Radiological Environmental Operating Report covering the operation of unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall ..the results of analyses of all radiological environmental samples and of all environmenta ifI'tion measurements taken during the period pursuant to the locations specified in the t .ures in the ODCM, as well as summarized and tabulated results of these analy.e1Gd me11." ments. In the event that some individual results are not available for inclus*i6Mth the repopk.. report shall be submitted noting and explaining the reasons for the, g results. Thedata shall be submitted in a supplementary report as soon as 'le.

0. .ýsu 1. m in .udc c 1-aNote-A single submittal may be made for ANO cobndheesci that-a-e-common to both units.) .

"Move.note up.

Q')

W,.

ARK.A.NSAS -- UNT2 6-20 Amendment No. 60,94,,57,493

ADMINISTRATIVE CONTROL 6.6.5 CORE OPERATING LIMITS REPORT .COLR)

ADMINISTRATIVE 4.47-9-3. __ -roCore operating limits shall be established 2rior to each rel ad

.. o~r..pro.t~o.an~y..rea...n.q. .of.a r ply.d*[cge and b.documented bshlel in the CORE OPERATING LIMITS REPORT for the folowin'o.te-*h';ehoad.

3.1.1 .1 Shudowvn Ma r in..T. > 2000F 3.1.1 .2 Shutdown Mjargin:.T .;200OF 3.1.1 .4 Moderator Temperature Coefficien 3.1.3 .

CEA Position 3.1.3 .6 Rep~.eta And Group CE/.:*...s 32.1 L..inear leat Rate 3.2.3 Azimuthal Power -Tr 3.2.4 DNBR Margin 3.2.7 Axial Shape index

,.,....................... ..... ..... ...b.The analytical methods"U06-l, to n theran 4... nltia ehos(se ..... o*.*ieth0 i cooe~jrtn ere tg limits Wrdressed .... b..fY.-4 hh e--.Indiill-k be those previously revi n appr ,.by the NRC.--- fe............0N4..,

specificall i heim .

1) 'The ROCS and DI *omp es lear Design", CENPD-266 P-A, 4%;_83 (Met I..l0abia s and 3.1.1.2 for Sh uia9R ins, 3. MTC, -:'6 for Regulating and Group P C sertio -tamits, a .4.b for DNBR Margin).

2)Control El *nt Assembly Ejection Analysis," CENPD OUNA J0.1607o (et ology for Specification 3.1.3.6 for a R Grotp* Insertion Limits and 3.2.3 for Azimuthal k....3) 3) "F" I Combination of Uncertainties, CEN-356(V)-P-A,

.aed Revi O1g-P.'* May 1988 (Methodology for Specification 3.2.4.c and 3.2.4.i r DNBR Margin and 3.2.7 for ASI).

"Calcfe Methods for the CE Large Break LOCA Evaluation Model,"

I- C~N~132-P, August 1974 (Methodology for Specification 3.1.1.4 for

~'* 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7

5) "Calculational Methods for the CE Large Break LOCA Evaluation Model,"

Additional pages CENPD-1 32-P, Supplement 1, February 1975 (Methodology for will be added as needed when clean Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for pages are created. Azimuthal Power Tilt, and 3.2.7 for ASI).

6) "Calculational Methods for the CE Large Break LOCA Evaluation Model,"

CENPD-132-P, Supplement 2-P, July 1975 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

ARV.AM.SAS UNIT 2 6-21 6-21Amendment No. 157,1654,169,179

7) "Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS," CEN-132, Supplement 3-P-A, June 1985 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

8) "Calculative Methods for the CE Small Break LOCA Evaluation Model,"

CENPD-1 37-P, August 1974 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

9) "Calculative Methods for the CE Small Break LOCA Evaluation Model,"

CENPD-137, Supplement 1-P, January 197 thodology for Specification 3.1.1.4 for MTC, 3.2.1 for L"AW-Ieat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for As1 ARKA..NJSA$ UNIT -2 6-21 6Amendment No. 157,164,169,17-9

ADMINISTRATIVE CONTROL (AU Al)

I 6.6.5 CORE OPERATING LIMITS REPORT (COLR) (Continued)

10) "Calculative Methods for the CE Small Break LOCA Evaluation Model,"CENPD-137, Supplement 2-P-A, dated April, 1998 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

11) "CESEC-Digital Simulation of a Combustion Enpineering Nuclear Steam Supply System," December 1981 (Methodo/l r Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margin, 3.1.1.41.04_04C, 3.1.3.1 for CEA Position, 3.1.3.6 for Regulating CEA an P Insertion Limits, and 3.2.4.b for DNBR Margin).

12) "Technical Manual for the CEN.T.' de,' CEND -.P-A, February 1991 (Methodology for Specificati .1.1 and 3.1.1.2 utdown Margin, 3.1.1.4 for MTC, 3.1.3.1 f Position 3 1.361for3 .frg 1*gtting and n

Group P Insertion Limits, ý,2.4.b foriNBR Margin.

13) Letter. O.D. Parr(.NRC) to F. frC;E), dated June 13, 1975 (NRC Staff Review of tJ"PoMbustion E eringECCS Evaluation Model).

NRC approval fo. ion and M methodologies. .*;..;...:.'.

~ )~~ n

14) Letterr ,*parr (NI .4 e(). dated December 9, 1975 (NRj F.'., ,viewoft osed ustion Engineering ECCS thodolo0gi ationg 01 chan NRC approval for g& !-*6.6.5.6'

15) L-96p1K A cherer (CE), dated September 27, 1977 EvalatR fTopic :s CENPD-133, Supplement 3-P and CENPD u eent., 1-P). NRC approval for 64-54 -. 6.5.9) methodology.

-16) Le'E N2CNA03, dated March 20, 1984, J.R Miller (NRC) to J.M riGnffi &L, SESEC Code Verification." NRC approval for "6U 6..-'

_6 5. )1methodology.

"1 X "Cal e Methods for the CE nuclear Power Large Break LOCA

\ **ion Model," CENPD-132-P, Supplement 4-P-A, Revision 1

"%§Wodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.'.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

"*.-".2--c.The core operating limits shall be determined so that all applicable limits (e.g.

fuel thermal-mechanical limits, core thermal-hydraulic limits, EmerQency Core

,,CoR,,..a*.sr.*:.(ECCSI limits, nuclear limits such as wm-*.*-D.,

a.drtransient analvsis limits, and accident analysis limits) of the safety analysis are met.

. .4-....d..The........ -- ---. ,O.R including any mid.cycle revisions or supplements. Ut-edeW;shall be provided upon issuance t,4-he-R ARK.,A.SAS - UNIT 2 6-21a Amendment No.

51 4.1II i I179, 1*2,497 I,1

C 4

I CN I

)

dl:

a

04 C*4 (6

c F

ADMINISTRATIVE CONTROL 6A4-1-AtATP,4'.4Qý4-P-RgfECG4:404-.P.ROGRAM All See PTS 6.4.d.

ARKA.NSAS UNI2 6-23 AmondmontNo.,

52,60,67. 116,193,209

ADMINISTRATIVE CONTROLS II 6446,.7 HIGH RADIATIOQNREA.

Al 6:,&"

(,D.&=.L.-E..*[,1. .. . -..

r.teon!h n

........A.--ra dia tio V:4dinv DOos W.44-eRts-4s Lt .tr onr t (-2.

poAe*wth*-r~r-eeopa~~t~e,-.--4.crof ,ev.. e n Al has-,,eeweetablosedm*,en.d.efornre exi.4 44Wersonel orequipeaneo.t.e yeaonts hY ho-wo- a hr, .res maeoened rea Q rmeer b.0, teae O1O&

-fdiat.M.pi Rariat-

..th an Are hll 1^tAecress hea shl a~Irjun~teNoExedn 10ribuat3 20iaio o thne contlv ed .bs fromloany SufcePnetrohatlb pledý be ...-am,¢,SA"*

toe to a vayo suh an area shall be barricadied and consicuous!' A

.... - .Lnt'

.........Yl Am............................ .-.......... A as a hfigh radiation -area. Such barricardes may be Opened as0 necessary to permit enytr or exit,of personnel or egu-nment

b. Access to, and aciite nec such areshl be contrlled bj means of.

Rad'afom: Work Permit P),__rfeau'valent that includes secification of o(R eb c.

radiation dose rates in the iaimediate work area(s) radiatio.n...........

radiation ornlection ooot.........

.......cti. eeq*u.ipment

.oro ..... aand

...... m.. dm.o...

measures Individuals qualified inradiation protection procedures and personnel and other appropriate

............................ I.... .............

continuously escoried by such individuals may be exempted from the LO1 reguirement for an RWP or equivalent while p~erfomgintheir assiqnea./

ARR.

PAhIAS UNIT-2 6-24 Order datedOctober 21, 1980 Amendment No. 21,29,60,91,98,116a, 209

emo C.tllfi SVSN"M~

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01 V~OO qV?kfM pol Ao)Q aq Ijetqs pUu eoju U01uptej q o~ s poisod -A~lsh 5:: aSU C4 He 9 MOJ Ue tpflS 01 AeMA~jUa tqoe=

110111,55 ml Xq p~jpuetjj a-)-W) AUP, WC11 JO~fO$U0efPe8 i tUO (u0Aiajjq 4. ind2 JfO~pel ij ue%.________

Jo wwlopa5u- U01 ~ei~jAeW4~ ~su~~ Llw IrWF fl~ ~eJflC)/.3 L~ UU41 Jtt'uJtj SGIUN O~S0U q' IM WONp~ Utle1.4 ! Z'L9 AJjUf9 jelU 01 JOIJO 11011P.11 Uin~e Iou smp bu-Jp.1q qo!kala p:,, 4*tvalou tlo~eiw4~~

tf *SE. J IseajeO1U a o 36-01J!. tuiapjq qo!-eid e aA.*39J 11 pue ~u~w~p ~q ~q ~ U!S-3M ~OSP J04;U AkpO OP.

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.10 'Julacl~as picwazIp wa tjjym -opemie S. jpig~XUs WJUJ- U --- C~PA4 §XUU1 puie %MieeL4 Ul Sai.ea 9SOP

.01,~C 1 3f4sa'5505u! Tis~norwuquoi wil 95170 Biuuoviuow uori4elpw

)eSOP UOWle*I-JSeIpCSI XrnUI1UOa -'00ra OI90A~p bU!JOluow iuolI elpew V~'

.ss~ssxd e8JU ur U ns UU!Jalua 1r'.0Mf JO enP!AIPul 40e" 'p s~a~L ulSA~)JWtA PUU OJ!~'~A~~ O u0o4Qa1Oid ;.o,4eIpeJ ju-s-d rjuim0~o: Ioi as;91 L~ 9JE AOD P 0Ua/e.-

weo 026Lt',PCjogqep() pe~p jepig CtlNM 8VSNvQPAU non~~

011) 765715-jo

0. .......

Si MUO(19S WaUe 9SOP S,a-VA&

40lis

>upO%:iUow :Of eipw %f' dfOjt O1fPAp- p V

PAJUMrý jpjqU ...... Q

. ...i .......... .

iiejo Ajkjua wuuinoe jo lauuosj~

IrO sp(OU,*gd f~u!.WP ae.. p9A301 UI.UO] lp1~4S "BIP pur-sJoC, (.1 'Z

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A RKANS~AS UNIT'2 6-24 Order dated Octeber 21, 180 Amendment No. 21,29,60,91.98,116a, 209

ADMINISTRATIVE CONTROL 6.5 PROGRAMS AND MANUALS AUlAl The following programs shall be established, implemented, and maintained. exceptas noted.

-446.5.1- OFFSITE DOSE CALCULATION MANUAL (ODCM)

The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program.-Ljd The ODCM shall also contain the radioactive controls effluent mnonatieaderaontos tha* environmental liologicalenvirnmhental included in the Annua:l monitoring activities and descriptions of the information Radiolokical Environrrmental .OQLeratinig and Radioactive Effi,*,i Rel*:&.de.Ar.._4 Licensee initiated changes to the ODCM:

a. Shall be documented and r9s of s performed sI be retained.

This documentation shall con' k 11

1. sufficient information to pp *,.-.,echang e(ýogether with the appropriate analyses or evaluations justn f....ange(s

2. aA determinatioQP.Pat the chatce(s) oft In

.'.tf Wlev1s of radioactive effluent control requirpfft1.CFR 20.1.pVi ` CFRIO 0 CFR 50.36a, and 10 CFR 50, Appendix lirhnot a' ffse y Im e accuracy or reliability of effluent, dose, or 5

setpoint. lations; B

b. Shall become e Wive a'pt a " "" Gf thOGeneral and to 3Vf .RC in the C. *ai' e SUbmii.fo t R -. form of a complete, legible copy of the entire ODCM Vsa part of or cor rentW ile Radioactive Effluent Release Report for the period of t.W.eport in which hangih the ODCM was made effectu've. Each change shall be id r':fiedeby marking the margin of the affected pages, clearly indicating the area of the pe'at was cha. ed and shall al-se-indicate the date (i.e., month and year) the change'i*smpi .

ARKA.NSAS UNIT 2 6-25 Amndpn N. 60,193

ADMINISTRATIVE CONTROLS 6-4W.5. 16 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995.

por*T... 1...the leak

.. into of th.. ......... ,'s ,,p' ,d exhaust isltion yraves sallbeyerified to be .6.1.2, unlces fth 4ihnacpale~eprT test has been succssful l heakage rate tested prior to enteringq MODE 4 fromr MODE r reous92days.

The peak calculated containment intemal gogtfre for the design b ss of coolant accident, Pa, is 58 psig. ME The maximum allowable containment leakag-alall =t. be 0.1% of containment air weight per day at Pa.

Leakage rate acceptance criternatel

a. Containment leakage rate a "* L During the first unit startup follow, test p A. a43 ce with this program, the leakage r POf.at tf"e critterel"r .. .<0.60 f'r the Type B and Type C tests and ~tf rT ~A tests

b. Air loa )ceptance- na are.

Ov'eaka Ie 5 0.05 La when tested at Pa.

"" *" or each door is _0.01 La when pressurized to > 10 psig.

The p*i ofei 1 T opn ta Containmn ionsLekaesating of a kn, Specifi s4t P"bram. not

r. apply to the test frequencies specified in the The provIos I f .oSpecificatio .0.3 are applicable to the Containment Leakage Rate Testing Program. N -,E A RKA*.*SAS - UIT-2 6-26 Amendment No. !7.6,225

Pages Only 2CAN0103XX Page 1 of X

2CAN0103XX Page 1 of x List of Regulatory Commitments The following table identifies those actions committed to by Entergy in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.

COMMITMENT

ML030370298

Contents

Text

SUBJECT:

REFERENCES:

Dear Sir or Madam:

1.0 DESCRIPTION

2.0 PROPOSED CHANGE

3.0 BACKGROUND

4.0 TECHNICAL ANALYSIS

5.0 REGULATORY ANALYSIS

Response

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