ML20234D229

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Forwards Rev 3 to Status of Facility Completion Rept,Per Insp Procedure 94300B.Licensee Projected Fuel Load Date Is July 1985.Reasons for Schedule Change Include Clearing of Items on Licensee Master Punch List & Completion of Testing
ML20234D229
Person / Time
Site: River Bend, 05000000
Issue date: 06/19/1985
From: Denise R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Thompson H
Office of Nuclear Reactor Regulation
Shared Package
ML20234D050 List:
References
FOIA-87-279, TASK-2.B.2, TASK-2.B.3, TASK-2.F.1, TASK-3.D.1.1, TASK-TM NUDOCS 8707070139
Download: ML20234D229 (53)
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JU.1 ' E95 MEMORANDUM FOR: Hugh L. Thompson, Jr. , Director, Division of Licensing, Office of Nuclear Reactor Regulation FROM: Richard P. Denise. Director, Division of Reactor Safety and Projects, Region IV

SUBJECT:

STATUS OF FACILITY COMPLETION FOR RIVER BEND STATION DOCKET N0. 50-458, REVISION 3 This forwards the status of facility completion report for the River Bend Station in accordance with Inspection Procedure 943008. It is the third revision of this report.

The licensee's projected fuel load date is July 1985. This has changed from June 1985 as stated in Revision 2. The reasons for the schedule change include the completion of testing, completion of required procedures, and the clearing of items from the master punch list. Safety-related buildings are now identified in " Boundary Identification Packages" (BIPs). As BIPs are turned over to the plant staff, all outstanding items on them are reflected on the master punch list. This results in a single punch list for safety-related systems and structures. The licensee's master punch list status on June 12, 1985, showed 7,195 open items. Of this total, only 1,539 were work items, and the remainder were nonwork (or paper) items. It should be noted that the licensee has already cleared over 28,000 master punch list items. The addition of BIPs for structures to the master punch list adds new items; thus, the overall closure rate appears less than that indicated by the number of items closed weekiy. All open items on the master punch list will be resolved to the Region's satisfaction prior to fuel load. Resolved means that an item is either cleared or determined to have no safety significance.

The licensee continues to work at preparing and verifying procedures to support technical specification surveillance requirements. The largest block of procedures for this is in the area of instrument and control (I&C). The licensee has identified 554 I&C procedures as required. Approximately 10'4 are verified and ready to support operation.

There are no outstanding escalated enforcement issues at this time. There are, however, many open inspection items (i.e., violations, deviations and open items). The open items list is attached to Enclosure 1. These open items will be resolved prior to fuel load.

f f RPB1/ - APBf DRSP JPJaudon/lk VEHJo3nson RPDenise

./j/85 L-/d/85 y/4/85 8707070139 870512 PDR FOIA

< l(j1 GRADER 87-279 PDR

e t If there are questions, please contact either Johns Jaudon (FTS 728-8140) or myself).

R. P. Denise, Director Division of Reactor Safety and Projects

Enclosures:

1. Items to be Completed Prior to Fuel Load
2. Preoperational Test Status
3. Construction Status
4. Status of Inspections Required by MC 2512, MC 2513, and MC 2514
5. Status of Allegations
6. Status of SER Open and Confirmatory Items Affecting Region IV cc w/ enclosures:

R. Martin, RIV J. Taylor, IE S. Stern, NRR K. Kniel, NRR R. Bangart, RIV E. Johnson, RIV J. Jaudon, RIV R. Taylor, RIV R. Bennett, RIV R. Caldwell, RIV D. Chamberlain, SRI B. Murray, RIV bcc w/ enclosures:

RPB1 RIV File l

1 a b ENCLOSURE 1 ITEMS TO BE COMPLETED PRIOR TO FUEL LOADING 1

I. The licensee will demonstrate to the satisfaction of Region IV that I management attention has been satisfactorily directed to ttose areas identified in the last SALP report as requiring either spe'ific or general improvement or continued activity in a specific area.

Previous SALP Evaluations I l

i Latest Previous Performance Category Performance Category Functional Area (8/1/83 to 12/31/84) (9/1/82 to-7/31/83) Notes A. Soils and Founda- Not Assessed (NA) NA 1 tions B. Containment and 1 2 1 Other Safety-Related Structures C. Piping Systems and 2 2 2 Support D. Support Systems 2 2 1 E. Electrical Power and 2 2 1 Supply and Distribution F. Instrumentation and 2 2 3, 12 Control Systems G. Safety-Related 2 2 4, 12 Components H. Corrective Action and 1 2 1 Reporting I. Quality Assurance 2 2 5, 12 (Construction J. Quality Assurance 2 NA 6 (Operations)

K. Design Control 2 1 7 l L. Preoperational Testing 2 NA 1 l l

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Latest Previous )

Performance Cctegory Performance Category Functional Area _(8/1/83 to 12/31/84) (9/1/82 to-7/31/83) Notes M. Plant Operations 2 NA 8 Preparation N. Emergency Preparedness 2 NA 9

0. Radiological Controls 2 NA 10 P. Security 2 NA 1 Q. Trainina 2 NA 11, 12 R. Management Control 1 1 1 S. Licensing Activity 2 . 1-Notes
1. No additional need for management attention was identified _ for this functional area.
2. Additional management attention should be directed toward as-built verification and drawing resolution.
3. Additional attention and resources may be needed to accommodate increased activity.
4. Source inspection should be improved to support spare parts procurement.
5. Quality assurance personnel should prov1de greater surveillance of actual construction. Staff should be provided to accomplish this surveillance in addition to performing document reviews and other activities.
6. There should be aggressive recruiting to fill positions within the QA organization.
7. There should be aggressive closecut of all IDI findings and monitoring of as-built verification.

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8. Evaluate completed walkthroughs of procedure in order to develop confidence in the internal procedure review and approval process.

Open permanent plant positions should be filled.

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9. Emphasis should be given to the timely correction of deficiencies identified during the emergency preparedness preoperational inspection.
10. Increased management attention is needed to assure that NRC identified concerns in the areas of radwaste systems, effluent releases, effluent monitoring, and transportation activities are completed in a timely manner.
11. Complete the definition of job qualifications and clearly define training and training requirements.
12. The Region is satisfied with licensee progress in this functional area and the functional area is currently satisfactory for fuel load.

II. NRC Region IV is continuing its review of licensee action on NRC bulletins. l III. NRC Region IV is continuing its review of Construction Deficiency Reports (10 CFR Part 50.55(e)) and Part 21 items. The licensee has reported approximately 300 items, including potentially reportable items. The current status of open reports is:

o Number of reportable items reported as 1

" Ready to Close" by the licensee o Number of items determined by the licensee 0 to be nonreportable and which the Region has not yet reviewed o Number not reported " Ready to Close" by 28 the licensee IV. The licensee will resolve to the satisfaction of Region IV the open inspection items delineated in Appendix A to this enclosure.

V. Compliance to Appendix R requirements was inspected by a team during the week of April 1,1985. The most significant inspection finding was that the licensee had not analyzed effects of fire induced spurious signals outside of the control room. A followup by Region IV will also be required to verify completion of fire stops and cable tray wraps and other minor items.

VI. Followup to the CAT inspection has been addressed in inspection reports-50-458/84-36, 50-458/85-01, 50-458, 85-10, and 50-458/85-21. Items remaining are being tracked as open items. Followup on the IDI inspection has been completed except for four issues referred to the Office of Nuclear Reactor Regulation by IE. These four items were:

I e e o Deficiency D4.3-3, Effect of Torsion / Rocking in Amplified Response Spectra o Unresolved Item U.14-1, Recoupling of Control Rod Drive Piping and Supports o unresolved Item 4.5.12-1, Standby Diesel Generator Lubricating 011 Circulating Pump Motor Qualification o Unresolved Item U.6.7-1, Periodic Test of the Standby Service Water System VII. The final draft of the Technical Specifications was checked against installed equipment by a Region IV inspection team April 29-May 3, ,

1985. Minor problems regarding requirements have been referred to NRR . L for resolution. This inspection found that many licensee procedures were not completed or had errors in them. It was concluded that the licensee's procedures to implement Technical Specifications would require an i in-depth reinspection. The inspection report for this inspection is still under preparation, but the licensee was advised of the extent of the problems found by the exit meeting and a Region IV letter dated May 10, 1985.

Appendix: A List of Open Inspection Items i

j I

I I

. . Appendix-to Enclosure 1 ,

i E![S.!!!E!I EE'hEEII55E!5E5Eh B;- 1-0-01 Areas alth inadequate spatial se;araticn of d;visict.a! cables.

!!:ttil 54-c; 'J-01 Errors on radic;ract.:c filr anc report of melc. !!tge 64-C:-0-02 Radiographs net pro;erly irterpreted by ESU. !!;g 54-0:-V-03-S? Failure to sent racio;racnic cual:ty recu;reteits. it;;h B4-06-0-01 RF crga71:ation ar.d sar.5;eler:

controls, dyrrn 64-06-0-02 EB staH qualificaticas, tyrriy 64-06-0-0' Nuclear training dept. orga-iza-tics, and adsir, procedcret.

DSECi!

E4-(s-C-0 Es .er al Es;;o; st Trair.:r.;.

%: h 24-Ot-0-05 Fes;:ratcrr pr:tecticr training fer radiattor. crter. Grrg E4-06-006 EF te:hnician training and qualification. G;rg:

El-5s  ? Exterr.a; rac;st.cc, s.ccs. s

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E4-(:-l-M f espirato"y prtte:tict p*c;rar.

UsClit 84-0e-0-!! ALARA pregras. ggrtgy 64-06-0-15 RF instrumen:atior and equip-een: cal;trat:ct pro.; ras.

EiC[it 54-Oi-0-16 FF fa:ilities. [s;[jg S4-06-0-17 RF epipsent & expenda:1e supplies, turray E4-0:-0-20 Flant air fic characteristi:s.

CaCCt:

i E4-3-0-2 N5E5-07 7, Ites !!.E.2. I E9CE!!

l 64-06-0-23 NURE5-0737, Itess II.B.3.

EEtif 64-06-0-24 NUREE-0707, Itess !!.F.1-1.

UECif i

i 64-06 + 2 kAEE-F3', Itsa II.F.1-:

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.M.a.* . .a 34-06-0-:6 NCREE-07;7, !!es !!.F.!- .

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.x.7 n-E4-Oe-0-:7 NUREE-07'7, Itea II;.I.1.1.

.th.rr..a.v El-:5 .s. :  :.es.' ;+ s :- -

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t 34-:5-J-04 L1:ersee traci1r; ei eteratsent to the hE;. [t!!;!tlji; B4-12-3-01 Fending amendsent of tee FSAE organi:ational figures. jag; B4-12-0-0; Fending cos;letten cf training.

etraining progras. [jg; E4-!2-0-E Fevise R!3 ER-CLS Tatle 6.2-1 for accuracy, tatt 24-1:-0-04 Operability of the seteore!c;y tener and calibratter.. [jg; El-12-2-05 Audit cf envircr,ssr,tal r:.1 crir.; pr:: ac. iii; 64-12-0-06 Audit of radiological analyses contractor. ligt E4-I'-U-01 Coaxial cable separating fres connectcrs. [!;ttli .

B4-14-0-01 Managesent control pro:edures.

Sllti E4-14-0-:: Ea:lologi:al effiuer: te:hrl:a1 s;ertil:aticns. b;ilti E4-14 C Liquidradmastesysters.Eg[lgi E4-14-0-04 Baseous racmaste sistess. Ugilty 54-:4-: .'5 Ef41 cent release pr::ecr es.

b;ilix i

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e EA-!L- -C' Ea:lat:cn a: rat: ring systeas, belle:

64-14-0-02 f.ir clear,Ing filter systess.

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E4-14-0-M Transportaticr. a:t2Vities. Uglity E4-14-0-10 kdits. Bgllig 54-15-0-01 Training / qualification require-sents for SS'.' Eng, personnel.

Ehi!!!Cl!!n El M i No persans.t cr tes;crary i:En-tificatter ta; cr :at.e. [g[j i

I 51-;7-U-02 Er.ut can par,el didn't ap; ear to support safety-rel'ated equipsent.

64-17-U-C i Electrical cable installations.

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E4-17-U-04 Na 0.:5' spacing between as;acent cables. [gi; I

Bi-::- M ' thesistr,lrati::re::st y trainir; p y an, h;;t;,,i; El -G-04 Ches:strptadic:ter.!str>progess.

!: LEE 21!!

B4-2:-D-05 Fest-accident sampling systes.

h!!b2!!!

. .:-: . :i: ..::es. e:e::c r:

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d.1,4.4.

4 i E1-::-2 Cres:stry/ rad::trer. stry analytical instrusentation.

!!!Eb2!il 34-21-0-0B Quality assurance progras, blihE!!!

Ef-: 0; frccecures, hig;;1g; j

E4-:4-0-0 Cable ties not ervironsentally i qualifies for 40 years service.

f Eatttil 54-25-C-02 hettin; ci cables tnter F.Pt'.

Eittill

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C:r.:s*2 n c4 as-tult pla .: ::

Fi4 ;e n :;u t:. igy. git B4-3:-V-01-E5 Failure to follos procedure

'laters'. Bennett B4-;4-0-01 Freoperational test procedure review. [hgggtl!!g I E4-05-0-01 It.terface betweer. emergen:y plan

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p at: plar.: ranager. !!irg E -!!-D-0 estr:te autt.;rity cf RPM planning group. laitj i

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54-:5-E-;5 Reascr.atle assuran:e tr6at F.EE au;sentation is isplesintec.

EtLLA 64-;5-0-06 Criteria fcr individaals to perfore energency response.

E!Ltd 54-!5-0-M Decueentatic. of pers:r:s ass:;n to eser;enty response. Ea;,r; E4-;5-C-Oi Authority of individuals assign -

to esergercy resporise. [ait!

S4-25-0-H Letters ci agreesent be revie ec, updated, certified, ar.ncally.

!!!EI M 'I  :' EIF

.C: tHe:tt.e retr: :ti.e to tri f erci! EF trair.ir;. [n;;

S4-25-0-12 Respiratory training essential to energency response. Baird E4-05-D-14 Verify each lessen /sodule objective is tested in exasics.

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4-!! '-:: h;;cri :: m ent:- it. ;12:s in is:

re:c cs roce. iiir; 54-:5 :5 Ccaplete installaticn, test, turr. aver and procedures. tilr(

E4 -22 Listing voi:e c:ssunicaticns link. laltg EA-:5 + :5 Exter at :!ocr tell at the t air.in; talldit;. iiir; 4

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l 11 E;-;I-;-4; Public ade ess s, ster 2r press triefing ro;t.. ijit! j E;-;5-0-44 \

lete the nor,-raciaticr.

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sanitoring systees. 13 ira t i

i E4-;5-0-46 Ocerability of the publi:

notification systes. [31;;

54-;5-0-49 Ccssunications systes i independence. faird

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24-;I-C-49 t Alars types en the paging systes.

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S4-!!-D-5: Minisus stockin; 'esel ui i

c;erational s;;;h es. ialt; )

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E4-;5-0-57 \

Hunan factors review of Elfs, l baird I

E4-;5-0-5B  !

State and local notificatic s. 1 I!![d 84-;5-0-59 Wotification of energency 1 classification, jgity ]

El '! te M rs:t tre party being calie: :

cah ta:i. ij!;p l 5 -;5-0 c'.

'niorsation te tne discoverer :J an injured person. }al;;

S4-;5- -6; Listing of all fully trainet at:

qualified persons. !!it; E4-;5-0-i4 tenoun:e relleis to all c:ncerret. ialt;

  • e e "i.. ~i't'.i. [d',;

~4-:5-C-b Rev;e= Elf re.len ard a;;rb.il process. liit!

24-;5-0-67 Re.ise E1F-2-001 to ac: as a reference EIF-2-005. !!!rs B4-;5-0-65 Correct EIF-001 pages 40 & 41 (IcenticalJ. li it( .

E4-05-0-d9 Resporsibility for classificatica and ceclassificat:en. jai;(

54-;5-0-70  !

Deploysent of offsite scnitoring teass. inrg E;-35-0-71 I Revise EIF-2-001 throtgh -005 j entil properly relieved. fairy 14-:5-0-7:

Frctected area notification systes. Pir!

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1 B4-;5-0-74 (

Obtain the NRC initial j information form. [jit!

E4 35-0-75 Telephone authentication schese fer initial notification. Saitg it. 5-C-h Instr.ctio's of ccliectior, of eraircrisir.tal TLIs. Inry 5t-:5-0-77 Only trair:ed persennel assigned to offsite radiological teas.

Edits 54-5-0-78 Instrt.sent cteck sources are aissing. Baird

t.;g-
.-7 'er ' san ey ct ' sr. calc te l

ti tr+:. int; '

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'84-:5-0-25 Fr:;er :tle of perstr, cc:r:iratin; ofis2te son:tcring l teas. jair; l

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54-05-3-51 Instructions cr. pluse cetersinatton. !!it!

1 1

E4-:5-:-E2 Farti: alate filter is glacee )

upstreas. jaitg j l

1 1

84-05-0-5; Frisa y i se:cedary eva uattan '

routes. jait!

6?- 5-3-84 Ve tiy Se:.10. .4.2.:.8 c:nforss mitt. the equipsent. !alty j i

!?-!!- -E! Ve ifs cErs:r.r.el a:::.ntatilits i a:::c;1.sre: m:tnin 30 sinL;es, l Eiits 64-05-0-26 Insure tnat personnel accountability is saintair.ed.

E!its I

i 84-35-0-90 Availability speciali:ed {

eg.ipsent fres 631! naret ase.  !

EilCE l E4-:5-:-91 Fc 1:.au; detriefing cf casagt 1

ntr:. teas (s). !!ir; l l

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E4-:5-:-i; P.ake cc re:tions ir. EIF-2-104.

131:E 84-;5-0-74 Ads:r.tstrative probles f cr glar.

se: tion distribution. Balts E4 ~!-: :-  : :-:e :e- aest t: is:Lde

.u.- i e. t  : 3,3 ,. ;.

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54-:5-0-75 Audit teaa sn:lude an Ir.:1.:hal with te:hnical expe*ttse. [alrg 24-:5-0-10: Distr:ttte transient public infernation within 10-sile E?Z.

!!its 64-5-3-104 RLacr control nus:Er in the crcchtre/ calendar. [31r; E4-35-3-109 ine opticn to delegate nctifications. [airg 84-:5-0-110 Review sources defining shift sanning, revise as necessary.

EaLCA I E4-:H -0; Fevien of irs that .ere isstet after NR: .nsps:ticr. 0;$i;u l

E4-36-U-04 NRR-NRC approval of spacing requirements. McNeill  :

84-36-V-05-54 i Docusent Control. M.c.N.e.i .l .l

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l E4-36-U-06 NER-NRC approval cf separatio requiresents. l;$e11 1 54-: -U-11 hRC audit of EQ ltess. ";bi!!;

E4-:5-0-01 Tests nct :n luded in prec; test prc:edures on generatcrs.

E!bui!

E5-Cl-V-'d-54 Contrcl ei nonconformance.

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:r: :: Ei. 3 : :. n 3 :

see $$$

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G5-7. s-0:-E5 Certain re:cr:s r.:t 6:::rcing tc l AE.*! Standards, g;Ngil!

25-0 -V-0;-Si Re:ords for steel celutns mere nct available or retrievable.

UE!!il!

85-03-C-0! Emergency prepare 3 ness deficiencies. laitg I i

l Bi-0'-042 Status bearcs de not p ovide k significant paraseters ar.d trend.

E!!Cd E5-C-0-03 Eevise so ccastnicatcr will be  !

dedicated to nettiitation resp. I EdiCE l

l E!-C~- M Interrectly assesse: :rcts:tive acti,n. {!ity I

85-03-0-05 Inforaal aid to energency classification. !aity l

85-0;-0-05 Provide for obtaining, using l setecrological data in TSC. la[tg 35-0:-0-07 Eecrient site survey a.d 10-EEF: l eaps . !5:. laite 55-C-0-25 Eeer;tasi:e c:r. taur.at:c, c:.;trel procedures. Ea!ty 35-C-C-(9 Prcvister.s for NEC site teaa space, n:t adequate. [ gird E!-3:-0-10 Classificatien and protection fer cifsite authorities. [ilt;

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E5-0:-0-12 !sprc<a E0F plant ra:iatict le.els, prctection acticr.s.

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!!![d i 25-03-0-1: Review ar.d revise contasination check for EDF. !!1t! -

E5-03-0-1A Elf-:-M1 incitded er, iciledup j nctification sessage ferss.

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E M 3-0-15 Frecedures arid inforsaticn te

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newssedia,tradegaate. fairy

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B5-03-0-16 Epace in JIC unadequate ter sedia representatives. [ air; E5-Cf-3-01 Rellatility ci the EH I setecrcicgi:a! data colle:: ion l

systes. !b3tgy l l

B5-06-0-01 50.59 reviens of tesperary

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hardware anc prececure ctanges. l Farrell l

B5-07-V-01-54 Failure to implesent procedures.

[2!8h!El!!0 2 M 7-0-:1 Failure tc seet a c:ss. tsar.'

identi'iec ty tha SFl.

Eh!!;g;1al; B5-10-0-01 Inspe: tier of Section 11 repair.

.. i ab..l.l s s.

E5-10-V-01-55 Ccapliance with weldirg saterial contrcl prc:ecares. 0;Ng111 E ! . :- :- *: r r, . ::s: .: ta;: :- srs:1 ge .ee

f 55-1 .2-? -54 It.deser. dent revie. :i ce!!;-

change calcalatt:r.s. "thiili S5-1: + 02-54 Control tesperary alterations.

M!ill 65-13-0-01 Engineering analysts cassitte: to 653 is unfinished. te;0ili 25-13-0-0; Maintenarice ;,rc;edures.

85-18-D-01 Safety-relatec display instrumentation ranges. Qll!!j,n 85-20-V-01-55 Inadeocate coerat:r.g trc edses.

!!GC!!!

E5-20-C-02 1splerentat:en of reference tracxing systes. iggtiti G5-20-0-03 Review of applicable design docceents for control relays. l j

EEBB!!! l 85-20 + 04-54 Failure to follcw prc:ehre in implementation 'I' ser:es.

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25 ~;-V-05-55 Failure :n pericraar.cs of t:si s

l delay control rela, set g: Int.

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25-21 + 01-55 Pcsting ti 10 CFF Fart ::.

McNeill E5-22-0-01 Frecedure ALM-00:9, paragract

5. M , intercretat:an. Fgt:11 M-::  : 4:'- :' : c .; 2:- :... - -

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35-2 {

h* prCgraf. tc a!Sess &"ecJa y 0 4 preker.tati be 4atete'iar. E.

fittell 'I 55-22-D-04 No definition of acceptable locking devices. [gttg((

65-22-3-05 P,cter operatec valve sair.tenan:e.

Eitt!!! }

55-:2-0-0:

Frocedura CPJ-10:e being revised.

Eittell 85-2:-0-07 ESU has estatlished centrols tc verify resets in aantal sode.

Eattel!

25-2:-0-05 530 has not identifiea ahich valves have operatcrs. [artgli ,

E!-:'-C-07 Scnedale ter preventative saintenance, not established.

Eattt!!

85-:2-0-10 Procedures revised to address contract saintenance personnel.

Etttill 25-: 11 Cleanl: nets ci plant systees have l

n:t teer estatlished. [i::iii.

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55-::-0-1:  :

0.:t at calibratica cattel.

Eittill B5-::-C-l~

Ko prograa for inservice e t

testingiinspe: tion requiresents.

Eittt!!

E5-::-:-14 No seth:ds ic initiating a design er r:E. [at:gli

!!-::-:- ! .u. :

r:..s :: :

o me e$

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E5-:: + 1e Unre.nese: saiet, questi:t as des:rited in 10 CFE 55.59.

[tLLtil E5- 2-0-17 Design and sodift ation char.ge requests. i Eittill I t

25-::-0-If Metheas for con: acting seiety i i

evaluations, nct estit!1sied.

EiEE!il l

E5 ~2-0-19 Methods for reviewir.g cetsgr.

2nput requiresents not estat-lished. [ittg!1 35-: -0 ~0 Metheds for perforain; trdepend-1 ent destgr. seriistations not estatlished. [attgil  ;

E5-::-0-01 Lest;n ir:erfa:es ha.e r:t been establ2shed. [attgl[ {

E5 ~:-0-:: l Final approval of design I

docusents net established.

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[attell B5-22-0-:3 Metbocs for centrollitig :nanges to appr:ved design change.

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55-: -U-24 Mett:ds i:r centre!!ir; c:sc:sts r cesignchange::c.,sents.[it;tl!

Y 35-::-D-:5 Eelease of ap; roved design char.;e l i docusents. iittgl! " '

B5-;;-0-:6 To assure cospitar.ce mitn design c ntrol. Eattg(( '

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acceptance testir.g. Fittgl;,

E5-2:-0 '0 F:st aediiscaticr. testin; ar.d j

acce; tan:e trite ta, lat;gli i

65-::-t-!! Feport cesigt. :targes ar.: accifi-

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cations to tiEC. [3t;til l

E5-::-0-:: Functional testing of equipsent I j

fcliening irstallatier.. [g;tgli i

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25-;2-:-:: l Eequirements f or perict:: revie. '

1:fted lead and jumper recctda.

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25-2:-0-01 i QA/QC Adstnistration. List not inclusive, G-list nct issued.

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1 85-2:-V-0:-E5 . Failure to follom procedures.

t (hitertain i 4

E5-:3-V-C_34 Failure te sanit:r tesperature.

Ebi!!!!!!!E B5-::-7-:4-24 Failure ts :a;:t ats gas se:er it.

III'iI Ci UII' hD$liS5kilU E -:: Pr05 100; retest cf the Hn: systeas at EE5. (Litti;liin B5-:4-0-01 in:epencent safety engir.eering Group. E!2:!!!

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E5-:7+( 4 ln:arpcratien in Fre:e:Le i AUE-0CI- hil!!!C 35-07-C-05 Changes to the prefire stratiegies. h!litig $

G5-:7-0-Oc Isciate ciesel generatcrs free sain ec :rcl race., tillikin (

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35-27-0-07 Spuricus si;ra! centerr.s. pending i

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B5-07-0-09 Eesolutica of consunications requirements. kl((Lin 1 1

i 65-27-0-09 Resolution of fire door assently ratings. hl!!!!n I

i 25 '-0-10 Cossittec to saae any sedtstcatiens reccare-ded by LL.

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55-:7 11 Espla:Esir.t ei fare p:.sps su::ica tut:erfly vah es. [ gill!10 1

-i 85-:7-0-1 C a;tettor, ar.:1 issuance ci all fire prctection station operating  ;

procedves. Ogilitig I 1

55-:2-0-01 Safe *.y cC& tittle ac:i M ty.

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Ei-4 M --C; Ins:s: tic.re::r:5. r.:Ns:1:

u

l ENCLOSURE 2 PREOPERATIONAL TESTING STATUS I l

)

The status of the licensee's preoperational tests is as follows: ,

Total number of tests l 101* 1 I

Number of tests completed and reviewed 78 {

(

Number of tests completed but not 8 reviewed Number of tests started 11 4 l

Number of tests not started 4

  • Number changed to reflect tests required for fuel load instead of all tests, i

1 l

l l

l I

1 l

. ~ .

ENCLOSURE 3

_ CONSTRUCTION STATUS .

i of May 17, 1985, icensee IIPs) to the has plant been staff. releasing equipment by " Boundary c ages" The Identification Pf Review of the current status by whole systems, istead of BIPs, indicate that out of 113 systems identified by ee the licens as ant staff.as of this report.eded to support a license to load fuel, 25 remains to quired systems have been turned over also.However, BIPs which contain portions of other ethe 40 systems approval process. requiring N5 stamp certification, 27 systems mpleted have co naining systems. A completion date has not been established for the f 1 i

3. 1 l

I d a a

q. . 7:.

i; i; ,

4t ENCLOSURE 4 STATUS OF INSPECTIONS REQUIRED BY i

J MC 2512, MC 2513, AND MC 25'.4 1 1

The MC 2512 inspection program and all completed NRC construction inspections J performed to date have been reviewed. Credit for the inspection efforts done by the Independent Design Inspection group and the Construction Assessment Team has been taken where applicable. The remaining MC 2512 module is as follows:

Module Number Description Percent Complete

  • TI-2512/11 New Initiatives 70%
  • Completion of this inspection is dependent upon completion of construction, N5 certifications, availability of as-built drawings, and the clearing of open i items. l This inspection is scheduled to be completed by fuel load.

The status of MC 2513 inspections is as follows:

Module Number Description Percent Complete l

70329 Preop Test Evaluation Verification NA l 70312 Preop Test Witnessing NA l 70317 Reactor Protection Sys Test Witness 80%

70322 ESF Test Evaluation 50%

(Integrated ECCS) 70325 Reactor Prot Sys-Test Evaluation 0%

70326 Loss of Offsite Power-Evaluation 50%

70323 ILRT-Test Evaluation 30%

70370 Testing of Pipe Supports 0%

70532 CRDM Test Evaluation 0%

70541 Emergency Standby Power-Evaluation 50%

70552 Remote Reactor SD-Evaluation 0%

[

35742 QA Program-Document Control 50%*

7 i

f

3 l

I Module Number . Description \

Percent Complete 35743 QA program-Maintenance 50%*

35744 QA Program-Design Changes 50%*

35745 QA Program-Surveillance Test 50%*

35750 QA Program MT&E 50%*

42450 Operations Procedures 90%

42451 Maintenance Procedures 50% J i

42452 Emergency Procedures 30%

71301 Technical Specifications Review 90%

79501 LWR Chem. Cont. 80%

79502 Plant System Affecting Chem. 80%

83522 Rad Protection-Preoperational 90%

83523 Rad Protection-Preoperational 90%

83524 External Exposure Control 80%

83525 Internal Exposure Control ,

80% ,

83526 Cont. of Radioactive Material 80%

83527 )

Facilities and Equipment 80%

83528 Maintaining Occup'.tional Exposure 80%

84522 1 Solid Wastes 60% i.

84523 Liquids and Liquid Waste 60% ' 1 84524 I Gaseous Waste System 60%

84525 Radiological and Chemical Confirm Meas. 75%

T12512/55 Emergency Preparedness 90%

81018 Management Effectiveness 0%**

81038 Records and Reports 0%**

[

81042 Testing and Maintenance L

n. .,. , ....e-- ,

0%** '

81046 Locks, Keys, Combinations 0%** ~

81054 Physical Barriers 3m -

0%**

81058 i~'"

Security System Power Supply 0%**

r 81064 Compensatory Measures 0%** ' "

81072 V' Access Control Packages 0%**

81074 Access Control-Vehicles 0%**

81080 Detection Aids 0%**

.....,,........I

. o. .

Module Number Description Percent Complete 81084 Alarm Stations 0%**

81088 Communications 0%**

81810 Physical Protection, S/G Info. 0%**

  • The remaining 50% of these QA modules are done after implementation (i.e.,

after licensing).  ;

    • Preliminary inspections of security have been completed; however, modules '

are carried at 0% complete pending lock down.

The status of MC 2514 inspections is as follows: i fiodule Number Description Percent Complete 35501 QA for SU Test Program 0% ,

72400 Overall Startup Test Log 0%

72500 Initial Fuel Loading Procedures Review 0%

72524 Initial Fuel Loading-Witness 0%

83521 Rad Protection-SU 0%

84521 Radwaste-SU 0% j 72502 Int. Crit-Procedures Review 0%

72504 Heatup Phase Procedure Review 0%

72508 Power Assession Procedure Review (A) 0%

72509 Power Assession Procedure Review (B) 0%

72510 Power Assession Procedure Review (C) 0%

72512 SU Test Procedure Review (B) 0%

72514 SU Test Procedure Review (A&B) 0%

72516 SU Test Procedure Review (A) 0%  !

72517 SU Test Procedure Review (A&B) 0%

72518 SU Test Procedure Review 0%

72526 Initial Criticality-Witness 0%

72532 Power Level Data Review & Evaluation 0%

TI2514-01 Confirmation of TMI Items 40%

TI2500-11 Emergency Preparedness 80%

ENCLOSURE 5 STATUS OF ALLEGATIONS RECEIVED BY NRC FOR RIVER BEND A total of 33 allegations have been received. Twenty-seven of these have been closed and six are still open. The status of the six open allegations is as follows:

Subject Source Status

1. Sensitive OI lead
2. Sensitive 01 lead
3. Cable Trays Anonymous RIV lead
4. Harrassment of Eng. Anonymous GSU lead; RIV monitor.

Staff (S&W) Will close in IR 85-43

5. Control Room Circuitry Craft Worker GSU lead; RIV monitor Problems to GSU
6. Drug Usage Anonymous GSU lead; RIV monitor

i

[\ . e. , s l Y.,,

l ENCLOSURE 6 l STATUS OF SER OPEN AND CONFIRMATORY ITEMS AFFECTING REGION IV The licensee will complete to the satisfaction of Region IV the following SER confirmatory action assigned to RIV for closure.

62 ESF functioning 1

1 l

l

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