ML20092M552

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Forwards Response Schedule for Draft SER Outstanding Issues Identified in Table 1.3,per 840608 Request & 840618 Commitment
ML20092M552
Person / Time
Site: Beaver Valley
Issue date: 06/28/1984
From: Woolever E
DUQUESNE LIGHT CO.
To: Knighton G
Office of Nuclear Reactor Regulation
References
2NRC-4-091, 2NRC-4-91, NUDOCS 8407020295
Download: ML20092M552 (14)
v • d • e


Text

_

e 2NRC-4-091 (412)787-5141 m

(412)923 -1960 Telecopy (412) 787-2629 June 28, 1984 Nuclear Construction Division Robinson Plaza, Building 2. Suite 210 Pittsburgh, PA 15205 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

Mr. George W. Knighton, Chief Licensing Branch 3 Of fice of Nuclear Reactor Regulation

SUBJECT:

Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 S.E.R. Outstanding Issues Status Gentlemen:

In accordance with your letter dated June 8,1984, and as agreed in our meeting on June 18, 1984, enclosed is a schedule for responding to all outstanding NRC questions and draft Safety Evaluation Report (SER) open items. Att achment 1 is a current list, as of June 22, 1984, which provides our understanding of outstanding issues identified in Table

1. 2 o f the draft SER. is a current list, as of June 22, 1984, which provides our understanding of confirmatory issues identified in Table 1.3 of the draft SER.

Items identified as " complete" are those for wh ich res ponse s have been provided and no confirmation of status has yet been received from the staff.

We consider these items satisfactorily closed unless notified otherwise.

In order to permit timely resolution of items identified as " complete" which may not be resolved to the staf f's satisfac-t ion, please provide a specific description of the issue unich remains to be resolved.

Items identified as "c lo s ed" or " confirmatory" are based upo n formal or informal communications or agreements with the staff.

Please inform us of any dif fering. opinion of status described on the att ach ed list.

The majority of the open items contained in your June 8 letter will require meetings to resolve.

Attempts are being made to schedule these meetings, and emphasis should be placed on arranging these meetings as soon as possible in order to maintain BVPS-2 licensing schedule. is a corrent list, as of June 22, 1984, which identi-fies draf t SER sections.and dates received, which were not included in the original draft SER dated March 1,

1984.

As this listing shows several draft SER sections still outstanding on your letter dated June 8, 1984, staff indicated that "...

all significant issues for this review have now been identified."

DLC is concerned that additional open items may result from the remaining draft SER sections and that these items will have a significant impact on BVPS-2 licensing schedule.

M B407020295 840628

\\

gDRADOCK05000 m

T.

.Unitsd Stctea Nuclect Regulatory Commicsion

Mr. G;rrga W. Knighton, Chief

-Page 2 As requested by the NRC, enclosed as Attachment 4.is a schedule for responding to the outstanding NRC questions. This list - also includes Power

Systems Branch mechanical questions which are being revised based upon a meeting.with the reviewer and for which no draft SER was provided.

Responses' to these questions were. originally provided in December 1983.

DLC has been working with the NRC Reviewing Branch on many of these ques-tions since their receipt.

DUQUESNE LIGHT COMPANY g,

E.UJ. Woolever Vice President GLB/wjs Attachments cc: - Mr. H. R. Denton, Director NRR (w/ attachments)

Mr. D. Eisenhut, Director Division of Licensing (w/ attachments)

Mr. T. Novak, Assistant Director Division of Licensing (w/ attachments)

.Mr. G. Walton, NRC Resident Inspector (w/ attachments)

Mr. M. Licitra, Project Manager (w/ attachments)

I

ATDO M NT 1 OJ1 STANDING ISSLES P110 POSED OLTISTANDING

RESPONSE

ISSUE SUBJECT DAE

, STATJS IETER NO. AND DAE 1

Pbtential for floodirg fran local intense precipitation 1

2 Flooding fran Peggs Run 1

3'-

Adequacy of the proposed tech spec for

. drought conditions 4/30/84 02nplete 2NRO4-049, 4/30/84 4

Adequacy 'of int &e structure silt nonitorirs progran 4/30/84 Complete 2fRCr4-049, 4/30/84 5

Boundaries of the Appalschian Platea2 Tectonic Province 4/30/84 Canplete 2NRO-4-048, 4/27/84 6

Maninun earthquake 4/30/84 Ctmplete 2NRO-4-048, 4/27/84 2NRO-4-072, 6/1/84 7

Gramd notion thirg soil properties into consideration 4/30/84 Cauplete 2 FRO-4-048, 4/27/84 2NRO 4-072, 6/1/84 8

Actual earthquake tin.s histories 4/30/84 Canplete 2NR04-048 4 / 27 /84 2NRO-4-072,, 6/1/84 9

Shallow earthquakes 4/30/84 Canplete 2 FRO-4-048,4/27/84 10 Vertical seisnic design a celerations 4/30/84 Qxnplete 2fR04448 4/27/84 2NRO-4-072,, 6/1/84 11 Tornado pressure drop rate calculations 4/30/84 Carplete 2rRC-4-047, 4/27/84 12 Oxrrete missile barrier design Canplete 2tRO4-018, 2/27/84 13 Site-specific response spectra 4/30/84 Otanplete 2tE04-047 4/27/84 2NRO4-072,, 6/1/84 14 Justification of pea sprealirg of floor

- response spectra Complete 2NRO-4-018, 2/27/84 15 3-ccmponent seisnic input vs. 2-conponert irput e/15/84 Conplete 2rR04-080, 6/16/%

16 Soil-structure interaction analysis of con-tairment asi int &e structure 6/15/84 Q2nplete 2NRO-4-080, 6/16/%

17 Significance of the couplits in structural response between nutually orthogonal axes of atructures 6/15/84 Q2nplete 2NR04-0 40, 6/16/84 18 Deviations of contairunent asign fran A9E Code Section III Division 2 6/15/84 Canplete 2NRO 4-080, 6/16/84 19 Ultimate capacity analysis of contaianent 6/15/84 Conplete 2tRO-4-080, 6/16/84 20 Deviations fran requiranents of ACI 349 code as mgpental by Reg. Guide 1.142 4/27/M Q2nplete 2NRO-4-047, 4/27/84 21 Structural audit action itens 4/27/M Caaplete 2rRO-4-047,4/27/84 22 Affects of cracked panel on dynanic nodelirs arti design 02nP ete 2NRO4-018, 2/27/84 l

23 Meguacy of re-assessed safety factors against sliding and overturnirg of contain-ment, anx. buildirg, arul inthe structure 4/30/84 02nplete 2NRO4-047, 4/27/84 o

b

r

. PROPOSED OLTISDWOUC RESPWSE ISSUE SURIECT DAIE SIAIUS IETIER NO. AND DAIE 24

'Ihrough-wall ledage cracks in noderate energy lines in contaiment 5/15/84 Closed 2NRO 4-4052, 5/8/84 25 Selection of postulated break locations 5/15/84 Closed 2tRC-44052, 5/8/84 26 Jet ispirgement effects 6/29/84 2

2NRO-4-4052, 5/8/84 27 Break exclusion zones 5/15/84 Confirmatory 2NRC-4-4052, 5/8/84 28 Pipe-to pipe impact 5/15/84-Ctznplete 2 nam-4052, S/8/84 29 Limited break areas 5/15/84

, Closed 2NRO-4-4C52, 5/8/84 30 Saturated or stbcooled water blowdown 5/15/84 Closed 2NRG-4-4052, 5/6/84 31 Design of pipe rupture restraints 5/15/84 Closed 2NRO-4-4052, 5/8/84 32 List of tramients 5/15/84 Closed 2tRO-4-4052, 5/8/%

33 Incation of systems to be nonitored durirg pre-op testig 6/01/84 Closed 2NRO 4-4052, 5/8/%

34 Criteria used for detenninirg acceptsility of vibration levels 5/04/84 Cosed 2NRO-4-4052, 5/8/84 35 Vibration nonitoring progran 5/04/84 Closed 2tRG-4-4052, 5/8/84 36 Canbining 3 conponents of earthquate notion 5/04/84 Complete 2NRO-4-4052, 5/8/84 37 Modes included in seismic analyses 5/15/84 Closed 2tRO-4-4052, 5/8/84 38 Denonstratirg seismic qualification 5/15/84 Closed 2NRO-4-4052, 5/8/84 39

. loadirs carbinations, systen operatig tran-stents, ard stress Itmits 5/15/84 2

2tko 4-4052, 5/8/84 40 INAC systen design 5/15/84 2

2NRO-4-4052, 5/8/04 41

-Design of safety ard relief valves 5/15/84 Closed 2NRO 44052, 5/8/84 42 Ibsign ani construction of A9E Class 1, 2, ani 3 canponent support 5/15/84 Ccruplete 2NRCr4-4052, 5/8/84 43 Preservice mi inservice testity of punps ard valves a-6/84 2

2NRC-4-4052, 5/8/84 b-12/84 c-6/85 44 Effects of rod bow on DNB 6/29/%

45 Flow measurement capability ani procedure 6/29/84 46 loose parts detection progran report 6/29/84 47 Docunentation of couplete ICC systen 6/29/84 48 Preservice inspections progran a-6/84 49 (bmpliance with Apperdix G 10CFR Part 50 6/99/84 OJmplete 2NRO-4-049, 4/30/84 50 Compliance with Appendix H 10CFR Part 50 4/30/84 Ocznplete 2:RO-4-O'+9, 4/30/84 51 Pressure tenperature limits 4/30/84 Octnplete 2NRO~4-OM. 4/30/84 52 3

53 Control roon haitability 6/01/84

. Im0 POSED OlTISTANDING

RESPONSE

ISSUE SURIECT DATE STAIUS IETIER NO. AND IAE 54 Inservice irispection of Class 2 arxi 3 components a-6 84 c--6 85 55 Design nodificatio-for autanatic rea: tor trip Canplete 2NRcr4-033, 3/30/84 56 Anticipatory reactor trip on turbire trip 5/25/84 Ocznplete 2NRC-4-086,6/20/84 57 P4 interlock Ctanplete 2NRO-4-038, 4/10/84 58 thdetectele failure in online testirs cir-cuitry for ergineeral safeguards relays 7/16/84 59 Service wter systen isolation on low healer pressure 5/31/84 Q3nplete 2?RO-4-086, 6/20/84 60 Normal letdom line relief valve 5/25/84 cmplete 2tRC-4-086, 6/20/84 61 Switchover fran injection to recirculation 5/11/84 Qxnplete 2NRO 4-056, 5/14/84 62 Main feedwater isolation 5/25/84 Omplete 2NRC-4-086,6/20/84

'l mntrol roon isolation 6/29/84 64 Stean generator level ecntrol arti protection Qmplete 2tRO-4-032, 3/28/84 65 IE ailletin 80-06 concerm 6/29/84 66 Independence between marual arti aitanatic.

action -

6/29/84 67 Power lockout for notor-operated valves Canplete 2I40-4-032, 3/28/84 68 asnote stutdom capsility 5/25/84 Ornplete 2NRO-4-079, 6/13/84 69 Bnergency response capability 5

70 Direct irulication of relief ani safety valve positions 5/18/84 02nplete 2NRO 4-064, 5/29/84 71 Bypass and inoperable status panel 5/25/84 Gmplete 2 tace 4-079,6/13/84 72-IE asiletin 79-27 7/02/84 73 Reactor coolant systen loop isolation inter-locks 6/29/84 74 Primary canponent coolirg water isolation fron RCP thermal bariers 6/29/84 75 PID controller nodification 6/29/84 Omplete 2tRO-4-086,6/20/84 76 High energy line bredcs arti comequential control systen failures 4/27/84 Qxnplete 2NRO 4-049, 4/30/84 77 Q)ntrol systen failure caused by inalfmetiors of carnon tower source or irntrunent line 7/06/84 78 Procedure to estimate extent of core danage Canplete 2NAC-4-042, 4/18/84 79 Backup post accident sanplirg through grab sanples for inline analyses Caaplete 2NRO-4-042, 4/18/84 80 Measurits radionuclide -oncentrations Qmplete 2NRO-4-042,4/18/84 8L Performance of PASS instrJREntation arEI analytical procedures Gruplete 2NRO 4-042, 4/18/84

4-150[" SED OLTISTMOING RESPON E ISSUE T HIECT DA1E SIAIUS 1ETIER NO. NO DA3E 82 Fire hazards analysis 5/15/84 Omfirmatory 2NRC-4-063, 5/23/84 83 Fire brigade 5/15/84 Confinnatory 2NRO-4-063, 5/23/84 84 Penetration seals 5/15/84 Closed 220-4-063,5/23/84 85 Safe slutdown 5

86 Alternate shutdown 5

87.

Hydecgen pipirg

-5/15/84 5

22 0 4-063, 5/23/84 88 Cable tray suppression 5/15/84 Closed 2mC4-063, 5/23/84 89 lbwer supplies for control roon ventilation 5/15/84 5

2NRC-4463, 5/23/84 90 Fire detection 5/15/84 Qinfinnatory 2NRC-4-063,5/23/84 91 Valve supetvision 5/15/84 Closed 2NRO-4-063, 5/23/84 92 Heactor coolant pumps and separation of safety-related conponerts in contairment 5/15/84 Confinnatory 2NRO-4-063, 5/23/84 93 control rom couplex 5/15/84 Confirmatory 2NRC-4-063, 5/23/84 94 Cable spealits roan -

5/15/84 5

2NRO-4-063, 5/23/84

.95 Exenption to 10CER 70.24(a) arri cks.cription of alternative to required criticality nonitors 6/01/84 Closed 2tRO-4-078, 6/13/84 96 Types, nebers, specifications for prt41e aitl laboratory HP instruerts 5/15/84 Closed 2 FRO-4-078, 6/13/84 97 1Yainirg/retrainirg for health physics go-fessionals arul verification that contractor trainirg neets 10CFR 19.12 requirenents Closed 2fR04-078, 6/13/84 98 Procedures generation package /IMI I.C.1, short-term accident analysts and procedures revision 7

99 Physical security 5/16/84 canplete 2tec-4-051, 5/04/84 100 Initial test progran 7/03/84 101 Radiological consegmnces of control rod ejection DBA.

5 102 Raliological conseqences of a small line bre* DBA 5/15/84 103 Raliological consequences of a stean genera-tor ttbe rupture DBA and review of operator actions axi systen performance 6/29/84 Canplete 2NRO4-086, 6/20/84 104 Raliological consequences of a steanline bre* outside secoiriary containnent 5

10 5 Raliological consegmnces of a loss of coolant DBA 5

106 Raliological conseqmnces of a fel harrilirg DBA 5

107 3

108 1MI Itens II.K.1.5, II,K.1.10, ani II.K.3.17 6/85 109 1MI Iten II.K.2.13 5

. PROPOSED OLTISTMOING

RESPONSE

ISSUE SURIECT DME STAIUS IETIER NO. #U DATE

-110 M Iran II.K.3.2 5

111 1MI Items II.K.3.5, II.K.3.30, ani II.K.3.31 5

112 Technical specifications 9/30/84 113' Detailed control roon & sign review 6/01/85 114 Safety parameter display systen 8/01/84 115 thowpack load on roofs 6/29/84 116 Extrane temperatures for site area 6/29/84 117 Affects of relocation of met tower 6/29/84 Complete 2NRO-4-079, 6/13/84 118 long tenn diffusion estimates 6/29/84 Ocznplete 2MO-4-079, 6/13/84

' 19 ~

Deviations to R.G.1.52 6/29/84 120 Containnent 'truun systen exha2st iodine renoval capability 6/29/%

121 Evaluation of RWSr failure 5

122 Water leakage into safety-relatal equipnent cubicles 7/02/84 4

123 Testirg of fmetional capability for water-tight seals 7/02/84 4

' 124 Accessibility of intake structure for safe stutdum 7/02/84 4

125 Adequacy of eter stops for construction joints 7/02/84 126 Floodits due to failure of non-seimnic Category 1 equipmcrt 7/02/84 4

127 Fan blade missile 7/02/84 4

128 Missile barrier for turbine driven aixiliary

. feeiwater ptsip missiles

//02/84 4

129 Pressurized container missiles 7/02/84 4

130

.1haperature arsi tressure semor missiles 7/02/84 4

131' 1brnaio missile protuction int aixiliary buildirs 7/02/84 4

lbrnaio missile protection of main stean vent 132 panels 7/02/84 4

133 Postulated pipe breaks outside cor ainnent 7/02/84 4

e 134

- Ebel pm1 nexinnsa heat loads 7/02/84 4

135 Light loal handling systen.

7/02/84 136 Harrilirs of heavy loals 7/02/84 -

4 137 Marine growth in standby service water systen 7/02/84 4

138 Verification of instrunent air quality in canpressed air systems 7/02/84 4

139 Equipnent armi florr drainage systen 7/02/84 140 (bnfonnance with Regulatory Guide 1.95 7/02/84 4

r:

' PROPOSED OLTISTANDING

RESPONSE

ISSUE SURIFCr DKIE SIAIUS IETIER NO. AND DATE

(

141 Conformance with Regulatory Guide 1.78 7/02/%

4 14 2 Seismic Categary I requirenents for cm-pressed air systen 7/02/84 4

143 Environnertal qualification and accessibility of essential equipnent housed in fuel buildirg 7/02/84 4

144 Safety classification of notor control centers 7/02/84 4

145 Air exhaust radiological monitoring systen 7/02/84 146 Protection of energency switchgear roan ventilation systen 7/02/84 4

147 Supplementary ledc collection and releme systen requirenents for safe shatdom 7/02/84 4

-148 Water hatner test of cordensate ard feedwater

,systen 7/02/84 149 Auxiliary feedwater systen,1MI Iten II.E.1.1 7/02/84 4

150 Seisnic qualification of equipment i,16/%

151 Ptmp arx! valve operability assurance progran 7/16/84 152 Favironnental qualification of equipmert Canplete 2NRO-3-096,12/5/83 153' Analysis of ccmbined IDCA ard seismic loads 7/16/%

154 Testing arti inspection of new fuel 7/16/84 155 01-line detection nethod to nonitor fuel rod failures 7/16/84 156 thderclad crackirs of forgirgs in rea: tor vessel 7/16/84 157 Review of structures systens, and canponents tnier Quality Assuran,ce Progran 5

158 PORV setpoint values 7/16/84 159 RHR operation requirements outside control roan 7/16/84 160 RHR overpressure protection systen 7/16/84 161 Qualification of RHR ptsnps inside contalment 7/16/84 162 Natural circulation test 7/16/%

16 3 Prograns anl procedures for contairment sunp operation 7/16/84 4,6 164 Review of off-site energency plans (m1A) 8 165 07-site eaergency plannirg 7/23/84 166 Baroneteric Fer.sure for contairment depres-surization analysis 7/16/84 4,6 167 Mass axi energy release analysis 7/16/84 4,6 16 8 Sd>canpartnent analysis (rea: tor cavity, stean generator ard pressurizer) 7/16/84 4,6 169 Contairment stmp design 7/16/84 4,6

~

. PROPOSE CLTISr#OING RESIONSE ISTE SURIECT DAIE STATUS 1EITER NO. AND DATE i

170 Post-accident hydrogen mmitoring systen 7/16/84 4,6 171 Type C testirg exclusion of valves 7/16/%

4,6 172 loogitudinal sections ard paraneters of Category I burisi pipelines 7/16/84 173 Stability analysis 8/31/84 174 Foundaticn data for rnain intake structure 7/16/84 175 Heasured, estimated ard allowable settlement data 12/85 9

176 Differential settlenents 12/85 9

Jl-'

177 Settlement nonitorirg progran 7/09/84 178 Densification of soils 8/31/84 179 Poll'danpirg valves 8/31/84 180 Soils' effective strength paraneters 7/25/84 181 Accuracy of SIIES prograa 7/25/84 182 Offsite power systens 6

183 Independence between offsite ard onsite power sources 6

184 Automatic loal tap changer 6

185 Testirs of offsite power transfer 6

186 voltage malysis for safety-related loads 6

18 7 Diesel generator testirg 6

188-Compliance with BIP-PSB-2 6

189 Diesel spnerator loadirg 6

190 Compliance with IEEE Standard 387-1977 6

191 lbwer reunal for selected safety valves 6

192 Automatic recimure of bredern after annual trip 6

193 Replacements for Class 1E loads 6

1%

Accident loadirs capacity of the diesel generator 6

195 Cmecting non-Class IE loads with Class 1E loais 6

1%

Cmplimice with G4 2 m>i 4 0

197 Compliance with GDC 17 6

198 Electrical ir&,erdence between pwer supplies 6

199 Coupliance with GDC 50 6

200 Inforwitian on evaluations of irdividual events 7/16/84 4,6

I

. PROPOSED OUISTROIfC RESP 0lSE ISSE SUBJECT DATE STAIUS IE11ER 10. #0 DATE 201 lbrbine trip event 7/16/%

4,6 202 Hea: tor coolant punp rotor seizure 7/16/84 4,6 203 Inadvertant boron dilution during refueling 7/16/84 4,6 1-IE ES:

I iled as a backfit tmder Generic letter 84-08 F

2Supplanental sthnittal to be prwided 31bt provided in draft SER

4. Responses hwe been infonnally transmitted to the reviewer 5 Staff action only 6A teetirg with the ERC Reviewirg Branch is required before response can be finalized 7No response required 8 DIE is currently arrargirg r unagement meetirg with NRC to discuss this iten 9Information will be wailable on the required figure and procedures by 8/31/M I PROGbM I PIOCEDURES 10R VALVES & PUMPS
  1. ISI PROGRAM

r ATIA0MNT 2 CCNFIRRIORf ISSIES

.0UISTANDDU ISSUE RIBJECT STATUS IETIER 10. AND DATE 2RO-4-047 4/27/84 1

Operatirg basis earthquake Qinplete 2NR04-072;, 6/1/84 2

Stress and strain levels of key structural elements Canplete 2EC-4-047,4/27/84 3

Floor response spectra a comtirg for 3-canponent earth-quake irput Otrcplete 3RO4-080, 6/15/84 4

5 Exanination of stean generators 6

7 Main N isolation 8

CR isolation on high radiation signal 9

Automatic openirs of service weer systen valves 10 Accident nonitoring instrunentation positions 11 Cold leg acetsm21stor MN position irdication 12 Table 1.9-2 by product, nource, arti special ruclear material descriptions nine nonths prior to fuel loading

@71.14B 1 13 Verification that cobalt use in primary systen has been minimized @71.10 Closed 3R04-078, 6/13/84 14 Omtainnent h*

rage raliation nonitors six nonths prior to fuel trg @71.14a.

Closed 2NRO-4-078, 6/13/84 15 Verify that INS airborne radioactivity nonitors closed 2NRC-4-078,6/13/84 16 Quality assurance progran requirenents Closed 2NRO4-078, 6/13/84 17 Peak pellet design basis 18 Specification of fuel parareters 19 Rod bowirg analysis 20 Wel rod internal pressure 21 Cicddirg collapse tine 22 11se of aistenitic stainless steels

  • Not provided in Draft SER

~

ih I

ATTA0MNr 3 DRAFT SER SECTICNS At0 DAIES PROVIED Section Date

-Section Date.

Section Date

,Section Date Section Date

^2.1.1 5.2.2 06/01/84-9.1.1 05/22/M 10.4.9 05/22/84 15.3.3 06/11/84

-2.1.2 5.2.3 06/01/84 9.1.4 05/22/84 11 05/04/84 15.3.4 06/11/84 2.1.3 5.2.5 05/22/84 9.1.5 05/22/84 11.1 05/04/84 15.4.5 06/11/84 2.1.4 5.4.1 9.2.1 05/22/84-11.1.2 15.4.6 06/11/84 2.2.1 5.4.7 06/01/84 9.2.2 05/22/84 11.2.1 05/04/84 15.5.1 0611/84 2.2.2 5.4.11 05/22/84 9.2.3 05/22/84 11.2.2 05/04/84 15.5.2 06/11/84 2.2.3 6.2.1 06/11/84 9.2.4 05/22/84 11.3.1 05/04/84 15.7.1 2.3.1 05/04/84 6.2.2 06/11/84 9.2.5 05/22/84 11.3.2 05/04/84 15.7.2 2.3.2 G5/04/84 6.2.3 06/11/84 9.2.6 05/22/84 11.3.3 05/04/84 15.7.3 05/04/84 2.3.3 ~ 05/04/84 6.2.4 06/11/84 9.3.1 05/22/84 11.4.1 15.9.1 06/11/84 2.3.4 05/04/84 6.2.5 06/11/84 9.3.3.

05/22/84 11.4.2 5.9.2 06/11/84 2.3.5 05/04/84

6. 2.6 06/11/ %

9.4.1 05/22/84 11.5.1 05/04/84 15.9.3 06/11/%

2.4.13 6.3.1 06/01/84 9.4.2 05/22/84 11.5.2 05/04/84 15.9.4 06/11/84 2.5.4 06/11/84 6.3.2 06/01/84 9.4.3 05/22/84 13.1.1 15.9.5 06/11/84 2.5.5 -

06/11/84' 6.3.3 06/01/84 9.4.4 05/22/ %

13.1.2 5.9.6 06/11/84 13.3.1 06/01/84 15.9.7 06/11/84 2.5.6 06/11/84 6.3.4 06/01/84 9.4.5 05/22/84 3.2.1 6.3.5 0601/84 9.4.6 05/22/84 13.3.2 06/01/84 15.9.8 06/11/84 3.2.2 6.3.6 06/01/84 9.5.2 13.4 15.9.9 06/11/84 3.4.1 05/22/84 6.5.1 05/04/84 9.5.3 13.5.1 15.9.10 06/11/84 3.5.1 05/22/84 6.5.3 9.5.4 15.1.1 06/11/84 15.9.11 06/11/84 3.5.2 05/22/84 8.2.1 06/11/84 9.5.5 15.1.2 06/11/84 15.9.12 06/11/84 3.6.1 05/22/84 8.2.2 06/11/84 9.5.6 15.1.3 06/11/84 15.9.13 06/11/84 3.10.1 05/18/84 8.2.3 06/11/84 9.5.7 15.1.4 06/11/%

15.9.14 3.10.2 c5/18/84 8.2.4 06/11/84 9.5'.8 15.1.5 06/11/84 17.1 06/01/84 3.11.1.05/18/84 8.3.1

% /11/84 10.2.3 15.2.1 06/11/84 17.2 06/01/84 3.11.2 05/18/84 8.3.2 06/11/84 10.3.1 15.2.2 06/11/84 17.3 06/01/%

3.11.3 05/18/84 8.4.1 10.3.2 15.2.3 06/11/84 17.4 06/01/84 4.2.1 06/01/84 8.4.2 10.3.6 06/01/84 15.2.4 06/11/84 19 4.2.2 06/01/84 8.4.3 10.4.1 15.2.5 06/11/84 20

4. 2.3 06/01/84 8.4.4 10.4.2 05/04/84 15.2.6 06/11/84 21 4.2.4 06/01/84 8.4.5 10.4.3 05/04/84 15.2.7 06/11/84 22.1 4.2.5 06/01/84 8.4.6 10.4.4 15.2.8 06/11/84 22.2 4.5.1 06/01/84 8.4.7 10.4.5 05/22/84 15.3.1 06/11/84 22.3 4.5.2 06/01/84 8.4.8 10.4.7 05/22/84 15.3.2 06/11/84 23 5.2.1 -

g t

' ATTACHMENT 4 Outstanding NRC Questions 2;

PAoposed Proposed

' Response Res ponse

-Question No..

Date Letter No. and Date Question No.

Date Letter No. and Date 100.3

'7/16/84 430.56 7/16/84

210.1 115*

430.57 7/16/84 210.2-9*.

430.58 7/16/84

_210.4.

7/03/84

'430.59 7/16/84 210.5:

3/85-430.60 7/16/84

~

210.6.

7/03/84 430.61 7/16/84 1210.7 7/03/84

'430.62 7/16/84 L210.8.

7/03/84 430.64 7/16/84 210.9 7/85-430.65 7/16/84 210.10

.7/03/84 430.66 Backfit

~ 11;11 7/03/84 430.67 7/16/84 2

210il2 7/85-430.68 Backfit "210.13 thru 430.69 7/16/84

~210.30 7/03/84 430.71 7/0'3/84 1210.31 9/01/84 430.72 7/16/84 i

(210.32 thru 430.73 7/03/84 210.39-7/03/84 430.74 7/16/84 210.40 1/85; 430.75 7/16/84 V210;41 6/85 430.77 7/16/84

'210.42 7/03/84 430.78-7/16/84

-210.43-17/03/84

-430.79 7/16/84-240.4' Backfit 430.82-7/16/84

'240.2 Backfit

~430.83

-7/16/84

240.4 Backfit 430.84 7/03/84 240.6 Backfit 430.85

.7/03/84 240.7 Backfit 430.86' 7/03/84 240.8 Backfit-430.87 7/03/84

. >270.1 6*

430.90 7/03/84'

.270.2 6/30/84' 430.91 7/16/84 271.1 12*-

430.92 7/16/84 T271.3 12*

430.94 7/03/84.

(F;

~ 271;4 12*

430.95 7/03/84 280.31 7/27/84 430.96 7/03/84 311.5

.311.6-7/03/84 430.98 7/16/84' J311.7 7/03/84

'430.100 Backfit 1311.8 7/03/84 430.102 7/03/84' 4311.91 7/16/84-430.103 7/16/84

410.51 i 'p"[

430.104 7/03/84 410.10 430.105 7/16/84 2410.24

~430.107 7/03/84

~410.52-430.108 7/03/84 430.11' 430.109 7/16/84 430.43 430.110 7/16/84 430.46' 430.113 7/16/84

'430.53-

~****

~

430.114 7/03/84 430.54:

_7/16/84 430.115 7/16/84 1430.55_-

7/16/84 430.117 7/03/84 s::

l 3,:. ;.:

.. Proposed

Response

, Question No.

-Date Letter No, and Date-

/

430;120

'7/16/84' 430.'1211 7/16/84-430.1221 7/03/84

-430.123 J7/16/84-430.124

.7/03/84 430.125 L7/03/84 430.126~

7/03/84-
430.127:

f7/16/84:

430.128 7/16/84 430.129,

7/16/84 1

-430.1321 7/03/84

~

430.133-(7/03/84

,430;1347 7/16/84:

430.136'

-7/16/84 430.138

.7/16/84 430.141

-7/16/84 430.144':

7/16/84

'430.146 7/16/84 440.73 7/03/84 er 440.74.

7/03/84 480.1 9/09/84'

' t90.6 9/09/84-480.25 7/03/84

'630.2 12*

630.16-630.17 :

f640.18'

~ 7/03/84

-640.30 7/03/84 NOTES:'

  • Months prior _to fuel load J ** Date z cannot be provided until meeting with NRC reviewer is complete
C**.Date cannot be provided until NRC evaluates response provided.

C*** Date to be provided in next status letter

_

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