ML20203B243

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Summary of 980126 Meeting W/Us Enrichment Corp in Rockville, MD to Discuss Applications for Certificate Renewal for Gaseous Diffusion Plants.W/Agenda,List of Attendees & Handouts
ML20203B243
Person / Time
Site: Portsmouth Gaseous Diffusion Plant, Paducah Gaseous Diffusion Plant
Issue date: 02/06/1998
From: Pravin Patel
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To: Pierson R
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
NUDOCS 9802240235
Download: ML20203B243 (47)
v • d • e


Text

.

- MEMORANDUM TO:

Robart Pisrson, Chi;f February 6, 1998

)

Spreist Projscts Branch j

Division of Fust Cycle Safsty and Safeguards 4

FROM:

Priya Patel Enrichment Section Special Projects Branch Division of Fuel Cycle Safety and Safeguards

SUBJECT:

MEETING

SUMMARY

FOR REh'EWAL APPLICATION MEETING WITH U.S. ENRICHMENT CORPORATION On January 26,1998, the NRC staff met with the U.S. Enrichment Corporation (USEC) to discuss USEC's applications for certificate renewal for the gaseous diffusion plants (GDPs).

USEC discussed plans to submit the annual update in the form of revisions to the susting application. USEC also discussed planned changes to sections of the Safety Analysis Report (SAR), the Environmental Compliance Status Report, and Supplementary Environmental Information. USEC suggested the deletion of " completed" issues from the Compliance Plan, however, NRC staff stated that the Compliance Plan should be maintained in its original form to document the regulatory tu:,nsition from DOE to NRC. The staff agreed that USEC should indicate completed items in the Compliance Plan and agreed that sections of the Safety Analysis Report (SAR) titled " Items addressed by the Compliance Plan" could be deleted once all com;...ance plan actions discussed in the section were completed. The staff also agreed that completed issues in the Compliance Plan need not be updated to reflect post-completion SAR changes. Furthermore, the staff also stated that the review nf the SAR update would not be coupled with review of the renewal application. The agenda, list of attendees, and USEC handnuts are attached.

Dockets 70-7001,70-7002 Attachments:

1. Agenda
2. List of Attendees
3. USEC Handouts cc: - Steven Toelle, USEC DISTRIBUTION:

l Dockets 70-7001,70-7002 9#tCTife"Centef PUBLIC SPB r/f I'

NMSS r/f FCGS r/f YFaraz Rlli Jacobson, Rlli DHartland, Rill PHiland, Rlli f

h SPB _

SPB SPB OFC SPB

't; SPB NAME kPPatel:ij

[ tin DATE

.2 / f /98

.0-/ 0 98 2 [/98

/ /98

/ /98 I

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C = COVER E = COVER & ENCLOSURE N = NO COPY G:\\1-26 sum pcp OFFICIAL RECORD COPY l'

,o 9902240235 980206 x

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1 1111 ll PDR ADOCK 07007001 H. H Hil I I Ill I le C

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  • i *
  • MEMORANDUM TO:

Rob:rt Pitrson, Chisf Spscial Prolscts Branch Division of Fus! Cycla Safsty-and Safeguards FROM:

Priya Patel Enrichment Section Special Projects Branch Division of Fuel Cycle Safety and Safeguards

SUBJECT:

MEETING

SUMMARY

FOR RENEWAL APPLICATION MEETING WITH U.S. ENRICHMENT CORPORATION On January 26,1998, he staff from the Office of Nuclear Material Safety and Safeguards, Site Facilities and Securi and Department of Energy (DGE) met with the U.S. tinrichment Corporation (USEC), to disc s the applications for certificate renewal for the gaseous diffusion plants (GDPs). USE

' ussed plans to submit the annual update in the form of revisions to the existing applicati USEC also discussed planned changes to sections of Safety _ Analysis Report (SAR), the En mental Compliance Status Report, and Supplementary Environmental InformatioNUSEC proposed the deletion of " completed" issues from the Compliance Plan, however, C instructed that the Compliance Plan should be maintained in its original form as a historical cument, an example of regulatory transition from DOE to NRC. NRC agreed for USEC indicate completed and closed items in the Compliance Plan and_ agreed sections of the Safe Analysis Report (SAR) titled "ltems addressed by the Compliance Plan" could be deleted once i compliance plan actions discussed in the sectiai, were completed. NRC also agreed t t completed issues in the Compliance Plan may be kept for historical use only and need n be maintained to reflect SAR changes. Furthermore, NRC also indicated review of the SA update would not be coupled with review of the renewal appitcation. USEC hopes to tran ' tion the SAR update by the end of March 1998. The agenda, list of attendees, and USEC h dout are attached.

Dockets 70-7001,70-7002 Attachments:

1. AgerMa 2, List of Attendees
3. USI:C Handouts cc: Steven Toelle, USEC DISTRIBUTION:

Dockets 70-7001, 70-7002 NRC File Center PUBLIC SPB r/f NMSS r!f FCSS r/f YFaraz Rlli Jacobson, Rlli Hartland, Rlli N

Hiland, Rill -

OFC SPB MB SPB SPB SPB NAME MPatel:ij boadley DMartin

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,L /.2 /98 M /k/98

/ /98

/ /98

/ /98 DATE C = COVER E = COVER & ENCLOSURE N = NO COPY G:\\1-26 sum.pcp OFFICIAL RECORD COPY

NRC/USEC Meeting Paducah and Portsmouth Applications for Certificate Renewal January 26,1998,1:30 p.m.

NRC Headquarters, Rockville, MD l

e The expiration date of the current certificates is December 31,1998.

USEC must apply for certificate renewal by April 15,1998.

e 76.36 Annual Renewals.

(a)

Afler issuance by the Commission of the initial certificate of compliance and/or an approved compliance olan, the Corporation hall file an annual application for renewal, as requ..ed by Q7t 31.

(b)

Information contained in presious applications, statements, or reports filed with the Commission may be referenced as part of the application, provided that the reference is clear and specific.

(c)

An application for renewal is subject to the requirements in {76.33 and must contain the following information:

(1)

The information specified in %76.35; or, (2)

A statement by the Corporation that the NRC may rely upon the information prosided in the presious application (s) upon which the existing certificate is based, except for:

(i)

Any proposed changes in the existing certificate of compliance conditions or technical safety requiremente; (ii)

Any proposed changes to the documents submitted with the previous application in accordance with 76.35; (iii)

Any changes which tha Corporation has made without pric.; NRC approval pursuant to 76.68; and (iv)

Any changes to certificate conditions or technical safety requirements-for which the Corporation has sought and received Commission approval pursuant to Q76.45.

(d)

The changes which are submitted as part of an application for renewal in accordance with paragraph (c)(2) of this section, must be in the form of specific changes to the documentation specified in Q76 35. The change must be marked and dated for easy identification.

Attachment I

e Planned Contents of Renewal Applications Reference will be made to the Annual Update Will also be submitted on April 15,1998 Will include plant changes implemented through February 16,1998 Application Volumes I and 2 - Safety Analysis Report (SAR)

SAR Sections 5.1 and 5.3 Application Volume 3 - Programs and Plans ECSR and SE1 Application Volume 4 - Technical Safety Requirements (TSRs) j No changes anticipated Compliance Plan - see preliminary markup

(

Admmistrative update Annotate the Table of Contents to identify completed issues Pull pages of completed issues Remove discussion of" closed" issue; from Introduction The Certificates Expiration date Changes in certificate conditions?

e Other Issues j

NRC Cutoff Date for Renewal - How to handle certificate amendment requests and Application revisions submitted after April 15 Transition to SAR Update

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Markup i/%/9b DOE /ORO-2026/R3 Plan for Achieving CompHance with NRC Regulations at the Paducah Gaseous Diffusion Plant i

e July 9,1996 DOE Compliance Plan Project Team 4

U.S. Depsmnent of Energy OakRidse Opensions OakRidge, Tennessee 37830

iii CONTENTS East PGDP COMPLIANCE PLAN ISSUES AND NONCOMP!.1ANCES CrrED IN mE APPUCATION....................................... v PGDP MATRIX OF COMPLIANCE ISSUES,10 CFR REQUIREMENTS, AND APPUCATION DOCUMENTS................................... ix ABBREVIATIONS............................................... xxi l

GIDSSARY................................................... xxv l

INTRODUCTION............................................... xxix l

COMPLIANCE PLAN ISSUES hat Transition from DOE Regulation to NRC 'legulation (CCmpl.t hd )............ 1 Update the Application Safay Analyms Report *

.........................2 l

Amoclave Upgrades *.(CCo>p ld.e d.)............................... 3 l C-360 Crane Upgrades *t.(ref.I tt e d )............................. 4 Nuclear Cruicalny Safety Approval D=.5. (ccmpl.d e d ).,............ 5 Nuclear Crmcalny Safety Approval implemenannn.(.tt.mphie.d )............ 6 Crincainy Accxient Alarm Symem Coveraget (complaa0.................. 7 Excepoons for Cruicalny Accides Alarm Synem........................ 8 RMunan P4 Procedures (C o m p ld.e d )......................... 9 l

Postmg of PMW Matenals*. (C C + p h. tad)....................... 10 l

Peh calibranan Source A-,i.(.cN di d)..................

11 t

NVLAP C6f- ='-m*

(compiam0................................

12 Fire Alarm Synem Reliabilityt. (templdsd.).......................

13 Fire P1otection Water Symem PCWiyi.(.Cupldid )..................

14 Fire Protection Eq 4 at (@~C.............................

15 Fire Pr~m Pih and Ha Work Perma Prcip.m (CCepldtd).......

16 l

Fire P4 Pre-Fire Planst.(Gofh id.).......................

17 PA-ine and Ts.r.si~h (conplaa0 18 l

i

  • These issues may not be fully runnbursable by the U.S. Dw
of Energy.

tThese issues are unique to the PGDP facilny.

raprm.v.s.7s96 e

k tv Managemem Comrols.........................................

19 Safmy emnmin=. (.cc.yMed.)................................. 20 Plam Changa and Configuranon M:=;- =......................... 21 M. n.,n.m. n+ -......................................... 22 opandons n, -........................................... 23 symans Appmsch m Training.................................... 24 Even Invemigadoes and Reporung Program.(Icmpk.h d )................. 25 Records Managemes and Denners Ceano! Program. *................... 26 Procedmas Pr,

  • ...........................................- 27 l

Q List (delemf)............................................. 2g Qualfry Assurance Pr gram knpi-ame

........................... 29 Public warnmg Sirens and Connoist (ccykhd )..................... 30 Pobuc Addrem S-t.(.ne e d.1.............................. u w

l E_.em Pian Suppon D~~ (c-waaf).......................

32

- l Trannng for Emergency P===== Organnanont (c@rao...............

33 Quality Courol Program for Low-lsvel Wane Duposal (conpamf).......... 34 Depised Uranian Managemen Plan *. (ccspk hd )....................

35 l

Seismic Capability of Buildings C-331 and C-335*t bew issue).............

36 l

Envirna==1 Trendag Procedmes*t hemp khd ).................... 37 l

High-Volume Ambiem Air Sampim t (Cqdd )..................... M

............d.................39d&M ).......

l E- - -

l=='-_

--5 undmg Pr+-

  • F

~

l rh -wi Safay Meh=nwi lmegrny rr _a l

HEPA Filar Symmm Taung* d@Mw........................... 41 l

Admini=rranve Controls on ovenime* ;=9kw cen

,............... fste cl)...

42 cey (mes.issus..

43 l

DOE Chemical Safety and Thid.Pany Use of Hazardous (%=lenk i

l Operanonal/ Safety System T P = L-4=- y @cw issue).................. 44 Ccm

~

l Codes and W (=:f c1)................................. 45 l

Criticalny Accident Alarm Symem-Horn Andibihtyt New issue)............ 46 l

10 CFR 21 hnp'=

ag Procedmes idelmaf).... l................... 47 ceaAwc l

Cascada Can Trip Punction R-6

= 't W).................. 43 l

UF. Leak Desctor Gdy Testmg* bew issue)..................... 49 l

Criticalny Accident Alarna for Nearby Buildings @ew issne)...............

50

  • These mines may not be funy reimbasable by the U.S. Depenmes of Energy.

11hese issues are unique to the PGDP facihty.

l *The U.S. Deparanem of Energy has no financel obligation relmed to this inne.

PGDP Rev. 3. 7886

y

~.

PGDP rW Pima Isomes and Neocampliances Cited in the Application 1sume' Dele (Nussber)

Ap% Citation Tr===== frun (1) ~

Update the Ap "- d-Safety Analysis Raport (2)

PGDP SAR 2.7 PGDP SAR 3.16.1 l

Upgrades (3)

PGDP SAR 3.16.2, 3.16.5, 3.16.10 PGDP SAR 4.3.1.1.1' 4.10 C-360 (4)

PGDP SAR 3.7.3.1.2, 3.16.7 [

l Nm: lear Crara Appewalh (5)

PGDP SAR 5.2.4.1 PGDP SAR 5.2.4.2 PGDP SAR 5.2.4.3 PGDP SAR 5.2. 4 PGDP

.2.4.5 PGDP 5.2.4.8 SAR 5.2.4.14 P SAR 5.2.4.15 PGDP SAR 5.2.4.16 Nuclear Crmcahty Safety Apprwal NP SAR 5.2.4.1 (6)

SAR 5.2.4.2 PGDP 5.2.4.6 PGDP SAR 4.9 PGDP SAR 5.2. 10 PGDP SAR 5.2.4.1 PGDP SAR 5.2.4.12

/

PGDP SAR 5.2.4.13

/

PGDP SAR 5.2.4.14 l

\\

h Accidem Alarm Synem Covera.e (7)

PGDP SAR 5.2.4.7 WW for Cruicality Accidem Alarm System PGDP SAR 5.2.4.7 (8)Nm\\

Prr*carm Procedures (9)

PGDP SAR 5.3.7.1 PGDP SAR 5.3.7.3 Postag of RadioecmMe00)

PGDP

.2 MP SAR 5.3.7.4 pMin cave Calibration Source y

NVLAP Cardrienr= (12)

[

%Qdennfind By USEC Fire Alarm Symem 3)

PGDP SAMW v

Fire Waser Sysamn Reliability (14)

PGDP SAR 5.4.8.2 PGDP SA' 5.4.8.5 PGDP Re.3,7/9/96

PGDP CampMasum Plan Innes ad Wpilances Ched in the Applicatina (centinued)

Ismae '11tle (Number)

ApM N Fi hrerm (15)

PGDP SAR 5.4.8.3 l

Fire Proesenen Procedures M8.4, 5.4.8.7 l

Fire Prossenon Pre-Fire MARJL4.8.6, 5.4.8.8 Pah[ransportanon(18)

PGDPSAR 5.5.1 Management Controis(19)

PGDP SAR 6.1.3 l

PGDP QAP A,W_ B-1.0 (leen 1) hfary (*>uvenieve== Ofh N;,;P cf_D_ A 71 Plant rhr and Cdruration Management (21)

PGDP SAR 6.3.6.1 PGDP SAR 6.3.6.2 i

PGDP SAR 6.3.6.3 m# SAR 5.3.6.4 PGDP SAR 6.3.6.5 l

PGDP SAR 6.3.6.6 Manwenance Program (22)

PGDP SAR 6.4.13.1 PGDP SAR 6.4.13.2 PGDP SAR 6.4.13.3 PGDP SAR 6.4.13.4 PGDP SAR 6.4.13.5 Operanons Program (23)

PGDP SAR 6.5.9.1 PGDP SAR 6.5.9.2 l

Synems ApproachtoTraines(24)

PGDP SAR 6.6.22.1,6.6.22.2 Event :.

=PEDIEEAR 6.9.8 Records %w and Document Castrol(26)

PGDP SAR 6.10.5.1 PGDP QAP AW B-1.0,isems 1 and 3 Procedures Prgam (27)

PGDP SAR 6.11.8.1 PGDP SAR 6.11.8.2 PGDP SAR 6.11.8.3 l

PGDP SAR 6.11.8.4 l

Quabry Assurance Ny.o h (29)

PGDP QAP A,e _B h"

ami Controis (30)

PGDP h

_E myr

'gy FGDP Re,3,7/9/96

vii PGDP Casnpliance Plan Issues and Noncesupliances Cited in the AppMe=*ia= (e==rinnad) 1 Issue Title (Nunnber)

Application Citation

}%iic Address System (31)

PGDP Em.-y Plan App-adhE

'N (5.4.1)

/

Ikan. App==dh E A _y Plan SMD-- -- = (32)

PGD [P" s- -

\\

(2.1

/

Training for Emergency Response PGDP "s.aj Plan A,ap-adh E (33) fl.2.1)

Qualsy Control Program for

-1.svel Waste PGD 7

Disposal (34)

Depleted Urab Management Plan (35)

PGDP Depleted Urannan m

Plan 4.0 Seismi: Capabilhy of Wild' y C-331 and C 335 PGDP SAR 2.7,3.16.1,4.10 l

m (36)

Eir, PGDP1ARah+.1 Egyh.;- = A - "

Au%Iers (38)

C+: _-

='-- :- g Fundag P ve.- (39)

D=ea==a% Punding Picy.-

Descripoon 7.0 Ch Mehaar=1 Integray Prey.-

PGDP SAR 5.6.15 (40)

HEPA Fiber Systems Tesang M AR5.3.7.5 l

Admminrrative Controls on Cp ([

Q l

DOE Nie=bMThird-Party 6 of PGDP SAR 5.6.

Fanhie=1= (43)

Operational / Safe:y System Trip Rd i=-i(44)

PGDP SAR 3.16.3 l

.I

\\-

4GDitSKR. Appendix A Codes and Crincahty Accident Alann System-Horn PGDP SAR 3.16.9 Audibihty (46) 15 CPR 21 1 ;-- --- -

h M 7) l

'-i@ (48)

MsAn 3.iirrH---

{

Cjascadeil Tt "

UF. lank Detector L --,ky Testag (49)

PGDP SAR 3.16.4 l

Crmcalsy Accident Alann System-Slayed Not idernfied by USEC Buildags (50)

PGDP Rev. 3.7566 e

ix PGDP Matrix of Campliance Issues,10 CMt Requranents, and Application Documents le CMt Requinenset AppHemeh Document (Section)

Issae11 tie (Number) 7d 6

Analysis Report

-Tramid5iffEnn DOE

~

(6.1.1

~

~

Angulanon to NRC

/

W'W 76.35(aX4), (6), and (8);

Safety Analysis Report Updase the Application 76.85 (P 2,3,4)

Safety Analysis Report (2) 76.3 a Safety Analysis Report (3) 76.87(cX5)

.5.4, 3.2.5.7. 3.4.7, 3.5.7, 3.

4.3.1..,

~

(2 C-360 Crane M[

76>3PX6), 76.85, Safety Analysis Rt w l

76.87( 11)

(3.6.9, 3.7.3.1.2, 4.3.5.1.2, (4) 4.7.2.3.1)

Techmcal Safety Re- -

(2.1.4.16, 2.1.5.2)

/

76.35(aX5), (6), and (7),

Analysis Report (4.4,5.2.2.

Nuclear Cnocalny Safety 76.85, 76.87(cX3)

Apprwal Dam'=ws (5)

Tv Safety (3.9.1.c, 3.ly

/

76.35(aX5), (6), and (7);

Safety Analysis Nuclear Cnocalny Safety 76.87(cX3); 76 (general)

(5.2.2.3, 5.2As, 5.2

,5.2.2.8, Apprwal

  • f = - f-s 5.2.2.9, 9)

(6)

Safety R T

d.9.1.c,3.11)

Quahty Assurance Proir-u (AM A-Section 1) 76.89 Safety Analysis Report (5.2.2.5)

Cnocalny Alarm Sysuun Technied Safety Roc--(2.6)

(7)

E P or Cnocalny 76.89(a)

Safety Analysis Report (5.2.2.5) f Accadern Alarm Systern Technical Safety R-po-(8)

(2.1.4.5, 2.2.4.3, 2.3.4.7, 2.4.4.2, 2.6) v PGDP Rev. 3. 7/9/96 D

x 1

PGDP Matrix et rP Lunes,10 CPR Requiremnemts, and A " ' Documunts (W

10 CPR Raqukummet AppEestion h (Seedom)

Isome TJte (Namnber)

[

1101(a),20.1101(c),

Safety Analyes Report shPW 76.

dx2)

(5.3, 5.3.1.3, 5J.1.5)

Procedures (9)

Technical Safety Requirunents 0.13) d W 20.1501(aX2 hafety Analysm Raport (53.1.7)

Posung 20.1902, 20.1 10) 76.60(dX2)

Technical Safety Regereneum 0.13) 20.1501(b),76.60(dX2kSafety Analyms Report (5.3.5) h Caltratior.

x j Source Accuracy (11)

Technical Safety R.@.- 0.}3f 20.1501(aX2),

SMAnalyns Report (5.3.2.4[

NVLAP Cer* men Tecluncal Safety Reqmren/

\\

(12) 20.1501(c),76.e0(dX2) ess 0.13)

Rapor/(5.4.2)

Phe Alarm Synem 76.87(cX4)

Safety Anald.

t

/\\

bli=hihry (13) 76.87(cX4)

Safety Report 4.2)

Phe Protecnon Water Symem ReliabGity (14)

T Safay R, x

(23A.8)

N 76.87(cK4)

Mfety Analyms Raport (5.4.3)

\\ Pke Prrwarswm

/

M (15) 76.87(cX4)

Safety Analyms Report Fire (5..'.1.1, 5.4.1.2, 5.4.2, 5.4.4, 9 4.6,

\\(16)-

[

5.4.6.3, 5.4.7) 76.87(cX4[

Saisty Analyms Report Pke Protection Fire

/

(5.4.1.1, 5.4.13)

Phas (17)

N Trampartation(18) \\

76.66(3),76.87(cX9)

Safety Analysis Report (5.5)

Packaging and N

/

.. PGDP Rev. 3,7566- ~ - -

x1 m

PGDP Matrix of Compliames Issnes,10 CFR Requ'r.memes, sad Applicaalan h (esatissed)

i. cpu

=

%- 9) w m.c

)

76.35(6)(3),76.35(a)(7),

Safuy Analysis Raport Managenset Camrois 76.93 (3.1.4, 3.2.5.1, 3.2.6, 3.3.4.7.4, (19) 3.3.5.7.4, 3.3.5.11.3, 3.3.6.7, 3.3.7.2, 3.4.8.1, 3.5.8.2, 3.7.1, 3.10, 3.11, 3.13, 4.3.1.2', 4.5.2.1.3, 4.3.2.3.5, 4.3.2.3.6, 4.3.3.2, 4.3.4.1.3, 4.3.5.1.1, 4.3.5.2, 4.3.7.1.10,4.3.7.3,4.3.( 4.4, 4.4.1.6, 4.4.1.7. 4.4.1.8, 4.4.1.9 4.4.1.10, 4.4.2, 4.4.3.1, 4.4.3.4, 4.4.3.6, 4.5, 4.5.1, 4.5.2, 5.1, 5.2.2, 5.3, 5.4, 5.5, 5.6.1, 5.7.1, 6.1, 6.2, 6.3, 6.4, 6.5, 6.6, 6.7, 6.8, 6 0, 6.10, 6. 1)

Technical Safety Rogerunsas (3.0)

Fi=d- =1 Nacasar Maurkis Control Plan (2,3,5.')

Emergency Plan (4.1,4.2,9.2) i l

Radioactive W me Managenset Progran (1)

Physical Securuy Plan for the Trumpormoon e SpecialNecisar Maasnaloflow Scrampe SI-T- = v (2.2.1,2.2.2)

Quality Asurers Program (2.1, 2.2) l Sace6y Plan for the Proesction of C! W Maast (1.2.2, 2, 3, 4, 9, 12, 13.2, 14, 15, 19, Appendous A-F)

Depland Uran' nn Maassansa Plan a

l (1.0)

Wi==% Pumius Progran (2.0)

zii PGDP Matris of Camapuunce issues,10 CFR R

=. and Applicatka Documunes (contimmed) 10 CPR *, '_.

Appuestion Documsat (Section)

Issue 'I1tle (Nummber) 76.3 6.68(a)(2)

S3fery Analyus Raport Safety C in argj6)-

(5.1.1, 5.2.2.2, 5.2.2.3, 5.2.2.8, f

5.4.1, 6.1.2 6.3.5.2.s.l.er61.2,..

10.2.2, 6:1T'C5, 6.1. 4.6, 6.11.8.4)

~

l Technical Safety Regenemones (3.10) 76.35(a)(4) and (6),

Safety Analysis Report Plant ChanSes and 76.51. 76.68, 76.85, (5.2.2.4, 5.2.2.6, 5.2.2.8, 5.4.6.2, Co4',w.iica 76.87(a),76.87(c),

5.6.6. 6.1.1.18, 6.2, 6.3, 6.4, 6.5, Mana8anent(21) 76.93, 76.95 6.6, 6.7, 6.8, 6.10, 6.11)

Qualsy Assurisce Pro 8 rain (2.3, 2.4, 2.6, 2.7, 2.8, 2.9, 2.10, 2.11, 2.13, 2.15, 2.17, Appsedex A-2.3,2.4,2.6,2.7,2.8, 2.9. 2.10, 2.11, 2.13, 2.15, 2.17) 76.87(c)(7)

Safety Analyms P. sport (3.13,3.13.1, Mair=== Fivy-3.13.2, 5.3.5, 5.6.5, 5.6.5.1, (22) 5.6.5.2,5.6.53,5.7.3,5.7.3.2, 5.7.3.4, 6.1.1, 6.1.1.11, 6.1.1.14, 6.1.1.25, 6.3.5.2, 6.3.5 J.3.6, 6.3.5.4, 6.3.5.6, 6.3.5.7. 6.4, 6.5.6, i

6.6.1, 6.6.3, 6.6.3.1;6.6.6, 6.6.14, 6.8.2.2, 6.8.2.3, 6.8.2.4, 6.10.1.13, 6.11.1,6.11.5,6.11-AM A)

Technical Safety Requinamens (3.2.2.b. 3.9.1, 3.15, 3.24)

Pi=damarent Nuclear Masrials Centrol Plan (Pitnre 2.3, 4.1, 4.1.1, 5.1.1, 5.1.2, 5.2, 5.2.1, 5.2.3, 13.1) hsay Plan (4.1.5,7.6, 8.2)

Quality Amurance Fiv (1-2.18, Appendix A)

Security Plan for ibe Pressenes of

.,_ j j C1LW Maser (6.8.1.8) e-PGar Re,. 3,7/9M

~

j

xiii PGDP Matrix oi CasspMance lunas,10 CIR

  • a '- ---

- and AppM = h (samtimmed) to CFR maquirement Appucadas Documsme (Section)

Issue 'ntle (Number) 76.35(a)(7),76.35(e),

Safmy Amlysis Raport(6.5)

Operadoes Programa (23) 76.87(cX14),76.87(ny6)

Techacal Safury Raquiremens 0.19) 19,20,76.35(aX5),

Safay Analys Report -

Symams Approachto 76.60,76.87(c),76.910),

(6.6, 6.6.1, 6.6.3)

TraWag (24) 76.95 Qiaby Assurance Progran (2.2.4)

Technical Saisty Requiramsas O.4) 7.

aX7),76.60, Safety Analysk Raport Eventinwmiganons[

76.11,

.120 (5.3.2.2, 5.3.4.2, 5.6.8, 6.1.1.16 Reporung G5) 6.51,6.7,6.9)

Technical Safury Requirements

/

O.10.5.h, 3.13, 3.19)

/

'.?:

n1 Nuenaar Control (1.4,1.5,1.6r.7, 8.6, 9., 11.4, 12

~

Easr Flen 0.2.1 kZ'2,3.3,4.1.14)

i~an for the Proescdon of s '

Classdad Mamar (17)

Physical Secursy Plan for the Transparadan of Special Nuclear Masurial ofI.aw Struessic S -- :"- =+ U.3.1. 8.3, 9.)

PODP Rev.3,M96 j

v

~

xiv PGDP Matrix of Camptbenee Issues, le CFR "-

^=- and.4;"="= Documwats (esattened)

I 10CFR*-f__ <

Appliendam Documment (Seenism)

Isume 'I1sle (Num6er) 76.3$(a)(7),76.93 Safety Analysis Raport (3.14.1,4.11, Records M -

_2 and

- ' 2.7, :i.2.2.3, 5.2.2.6, 5.2.2.8, Daa=== Conunt (26) 1.2, 5.3.1.2, 5.3.1.3, 5.3.1.5, 5.3.1.6, 5.3.1.7, 5.3.4.2, 5J.5, 5.3.6,5.4.5,5.63.5.7.3.2,5.7.3.4, 5.7.3.5, 6.2, 6.3.1, 6.3.2, 6.3.3, 6.3.4, 63.5.2.3.2.e 6.3.5.2.3.4, 63.5.2.3.6.a. 6J.5.2.3.8, 6.3.5.4, 6.3.5.5, 6.4.5, 6.4.7. 6.4.8, 6.4.11, 6.4.12.1, 6.4.12.2, oJ.12.3, 6.5.4, 6.5.4.2, 6.5.5, 6.6.2, 6.6.3.1, 6.6.21, 6.9.4, 6.9.6, 6.10.1, 6.10.2, 6.10.5.2, 6.11.1, 6.11.4. 6.11.4.8, 6.11.5, 6.11.6, 6.11.7) i Tehahl Safety Rw.-

e (3.6, 3.9, 3.10.6, 3.24)

Physical Securiry Plan for the Transporadon of Special Nadner Marial oflow Strategic Sb >r=== (4.2, 5., 5.4.1, 5.4.2)

Furdamental Nudear Manennis Control Plan (1.4, 1.7, 2.3, 2.4, 2.5, 3., 4., 5.1.2, 5.2,8.3,9.4,10.2,12.1, P 4,13.1, 13.2) hi-y Plan (4.1.9. 7.1, 7.2, 7.7, 8.1, 8.2, 9.2)

(corninued on wxtpage) v E IfT. I. 7M

xv PGDP Matriz et r=& muuss, it CPR Bagmirumunes, and Application Doomssemes (eautimmed) le CPR Requiruumsme Appihmeism Dem (sestism)

Issuelists (Numsber)

(MM&Pett)

Qualiry Amurame Progran (2.2.2, 2.2.4, 2.3.1, 2.3.3.1, 2.3.3.3, 2.3.3.5, 2.3 J.6, 2.3.3.7; 2.4.1, 2.4.3.1, 2.4.3.3, 2J.1, 2.6, 2.7.3.2, 2.7.3.5, 2.7.3.8, 2.7.3.9, 2.8.3.4, 2.9.3.3, 2.10.3.11, 2.11.3.1.4, 2.11.3.2, 2.12.3, 2.15.3.8, 2.17 2.18.3.8; Appedia A, Sections 1-1.2,1.3,1.4,1.5,1.6,1.7,1.8, 1.9, 1.10, 1.11, 1.12, 1.15, 1.17, 1.18, 2-2.2, 2.3, 2.4, 2.5, 2.6, 2.7, 2.8, 2.9. 2.10, 2.11, 2.12, 2.15, 2.17,2.18,3-3.2: Appendix C)

Secursy Plan for the Prcanction of ne w Mansr (2.2.6, 3.1, 4.7. 4.8, 4.9.2, 6.2.1.4, 6.4, 6.5, 6.6.3, 6.7, 8.1, 8.4, 8.5, 8.6, 9., 9.4,10.,11.,12.,13.,14.,

15.,16.,19., Appsadas F-1.A)

D==n% Punding Fiv.-

(4.0)

Depleted IJranima Management Plan (3.0) l Rahnactive Wame Managemen Progran (6.6, G.7) v MEIP Rev.3.WW96 t

_J

xvi a

PGDP Matrk of Caugdinace immes,10 CFR 8G _

% and Appuesden Documssmas (esmessed) le CFR Esquiremsat Appucatism Deamment (Seedom)

Issue Tide (Plundsar) 76.10(c),76.35(a)(7),

Saduty Analysis Rapm Procedures Program G7) 76.35(k),76.60(c)-(0, (4.3.1.4.4, 4.3.2.1.3, 4.3.2.3.5, 76.60(c),76.85,76.87(c) 4.3.2.3.6, 4.3.3.2,4.3.4.1.3, and (d),76.910),16.93 4J.5.1.1, 4.4.1.1, 4.4.1.6, 4.4.1.7, 4.4.2.1, 4.4.2.2, 4.4.2.4, 4.4.3.1*,

4.4.3.4, 5.1.1.1, 5.1.1.2, 5.2.1, 5.2.2, 5.2.2.2, 5.2.2.3, 5.2.2.6, 5.3.1.1, 5.3.1.5, 5.3.2.1, 5.3.2.2, 5.3.2.6. 5.3.2.8, 5.3.3.1, 5.3.4.1, 5.3.4.2, 5.4.1, 5.4.4, 5.4.7, 5.5, 5.6.3, 5.6.3.1, 5.7.3, 5.7.3.1, 5.7.3.3, 5.7.3.4, 5.7.3.5, 5.7.3.6, 6.1.2, 6.2, 6.3.2, 6.3.3.2, 6.3.5.1.1, 6.3.5.2.1, 6.3.5.2.3, /. 3.5.4.1, 6.4.5, 6.5.5, 6.6.1, 6.6.3.5, 6.7.1, 6.8.1, 6.9, 6.10, 6.11)

Technical Safety Ragesunear o.9, 3.10)

Fansrgency Plan (7.1,7.5)

Quauty Aasuranos Prograin G.2,2.3, 2.4, 2.5, 2.6, 2.7. 2.8, 2.9, 2.10, 2.11, 2.12, 2.13, 2.14, 2.15, 2.16, 2.17,2.18, Appendk A)

Radioacdve Wans Managemser Program (7)

Depised Urmdum Management Phn 00)

WVoI a, _. _ n 76.93 Sadsey Analysis Raport(6.4,6.3)

Quauty Aasurance Progresa W Qtary Amurs se Progran (1-2.18, Q9)

Appsedhas A amiC)-

Technical safety Raqukunsam 0.5) -

J

- warmlagSirens T

W-z 76.91(b) u.7, 6.2) 40 i Nn -

PMW Rev. 3,7/996

~

J

xvii PGDP Matris of Cemynmace Immaa,10 CPR PG

. and Appucadan hm (emudmand) le CFRItaquirusasat Appuers'a Documumt (Seedsm)

Isome Title (Nummber) 1(e)

Emergency Plan (5.4.1.1, 5.4.1.2, Pubuc Address 5.4.1.3, 6.2.1.2) 01) 76.91(m)

FJastgency Plan Emergency support (Plan Saunary,7.1.10).

76.910)

Emergsacy Plan T

for lhmergency (7.2.2)

Organizaninn 3) s 76.60(dX2),20.2006(d),

Wass Management Quauty Control Program Appenes F to Part 20 6.5) for Im ime! Wase Disposal (34)

Technical R.

(3.14) 76.4,76.35(m)

Safety Analysis Q.5, 3.5.1, Depised Uranhan 3. 5.2, 3. 5. 6, 3. 7, 31 8, 3.7, 3. 7. 1, Management Plan (35) 3.7.2, 3.7.

.3.4,4.3.

T*

Safety Requiremann

)

Plan (1,1,1.2, 2.1.2, 2.2.2)

Depked Uranhan Managenset Plan (1.0, 2.0, 3.0)

M% Pandag Progran (1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 4.0, 5.0,

[

6.0) 1 76.35(aX4),76.35(aX6),

Safety Analysis Raport Seimnie CapabGhy of 76.35(aX8),76.85 (2.1.1, 2.6, 3.1, 3.3, 3.4, 4.2.2.6, BuBdings C 331 and 4.6.1,4.7, Table 4.91)-

C-335 (36) f 20.

dX2)

Safety Analysis Report

" e 'r 1L 4 (5.1.2.7,6.11,6.11-Appendix A) -

07)

T Q.9.1, 3.1 20.1302(a),76.60(

dhalysis Report (5.1.4.2D Volume Ambisut Air Technical Safety Requiransas 0.16)_

, ~.

PGDP Rev. 3.wp6

A PGDP Matrix of Campumace Immes,10 CPR Rd-

u. sad Appuestian h (W

10 CPR

  • a_'

Appuenden Docenant (Section)

Issna11tle (Number) 16.35(m), 76.35(n),

Satory Analysis Report (6.3.3.2)

Doct- -

!= '-

76.83(a),76.83(b),

Funding N, (39) 76.83(c)

Technical Safety Requirmnents (2.5, 3.14)

I Radicactm Wasse Managemsat Program (3,4, 5.0, 5.1, 5.2, !J, 5.4, 6.1, 6.2, 6J, 6.4, 6.5, 6.6, 6.7)

Depised Uranian Management Plan (1.0, 2.0, 3.0)

Deco==ni-ing Fundma Program (1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 4.0, 5.0, 6.0)

)6: aX6),76.87(cX11)

Safety Analysis Raport r%=nb1 Safety (5.6.1, 5.6.5, 5.6.13.3, 6.4)

MehanWI 4

Program (

Tachnb1 Safety Requirements (3.15, 3.18)

M s.xy Plan (2.1.2-2.1.9. 2.

2.2.

, 7.3, 7.5, 7.6, 8,

= -1.12, 2.10, QAP (2.12, 2.12) 76.60(d),76.87(c),

Safety

' Report HEPA FDter Symems 20.1101(a) and(b),

(5, 3)

Teating (41) 20.1701 j

s N

i 76.35(e), 76.87(

Safety Analysis Report Aq.Gw Coetrols (6.5.93) onOv q2)

Technical Safety Regarements (3?9b) e f

xix PGDP Matriz et Campilmmet 1spnea,10 CIR # :, '

^=, and Applicadas h (candamed) le CFR ",_ ' _

Appucation Docuumsat (Secdam)

Issue Title (Namdier)

76..

76.87(cX11)

Safety Analysis Asport(5.6.14)

DOE N hl and y Use of echnical Safety Raqmrunaus (3.18, NWla 3

(43) d 7.6,8,1 Quality Assurance Progran (Appendix A) 76.120(cK2)

Safety Analysis Report (6.9)

Operanomal/ Safety Symem Trip R9 = i==i (44)

$6:3 d)

Safety Analysis Rep:r.t Codes and Standards t,

(2.4.3, 2.4.3.2, 3.2.3, 3.2.5.8, 3.3.4.5.1, 3.3.5.5.5, 3.6.7.7, 3.7.1, 3.12.6, 3.13.2.8, 4.3.1.5, 4.3.2.4.1, 4.3 J.1.2, 4.3.4.1.2, 4.7.1.3.2, 5.2.2.1,5.2.2.3,5.23.2,5.2.4.1,

.3.2.10, 5.3.2.2, 5.3.2.3, 5 J.5,

, 5.4.1, 5.4.1.1, 5.4.1.2, 5.4 16.5.2,6.6.6.1,6.6.

6.8.1,6.81 6.10.1.8,6

.1, Table 3.21, %

1, Table 5.3-4 T 1, AppendixB to SAR 6.11 T

Safety Ragmirunass

,, 2.2, 2.3, 2.4)

Quality Assurance Program (2.2.4)

Eswgency Plan (3,5.5.1.2,7.5)

Packaging and Transparanon Quahty Assurance Program (2.2.2) 76.89(a)

Safety Analyas Report (5.2.2.5)

Criticality Accidset Alann S, Morn Technical Safay Raquransas Andtury (46)

(2.1.4.5, 2.2.4.3, 23.4.7, 2.4.4.2, 2.6)

PGDP Bev. 3.7996 e

i t

I xx 3

PGDP Maarts of Campumace lames it CM Raquirumsmas, med Appucadse h i

i (esudensd) i It Cm Raquinneset Appusadam W (Bandsm) lasme'I1de (Number) 10 CPR 21 j

Procedures (

}

(dds8880 I

76.35(e),76.87(a),

Andysis Raport Cascade Cau Trip l

76.87(d)(3),76.87(dX5)

(3.

3.3.5.7.1, 3.3.5.7.2, Punction Requirammes l

3.3.5.7.4,

.7.1, 3.3.7 (48)

~

3.3.7.3,Pisure

.2.1, 4.(,3.2.n

.9.1 J.2, 3.3 21. Figure.

3.15.2.1

{

4.3

.2, 4.3.2.1.5, 4.3.2.1.,

~

. 2.2.2, 4.3.2.3.2, 4.3.2.4.1,

/

Table 4.3-2, Table 4.:-3,4.6.1.4,

\\

Table 4.7-15)

Technicalsafay Requirummes (2.4.4.12) 76.33(d),76.35(aX6),

safety Analysis Report (3.16.4)

UF. Laak Desecuor 76.123(c) sensitmry Testing (49)

Tecimical sassy Requiransen (2.1.4.1, 2.1.4.2, 2.2.4.1, 2.3.4.1, 2.3.4.2, 2.3.4.3, 2.3.4.4, 2.3.4.5, 2.4.4.1) 76.89(a) and(b) safety Andysis Raport Crincauty Accidset (3.17 ',5.2.2.5)

Alann Sysum>-Slaved Baudings (50)

Technical safety Raquiremsnm (2.6.4.1)

?

4 i

M

'a PMW Ber. 3. 7/Wpf

INTRODUCTION i

On Novenber 7,1995, itw Unhed Stasas Enr=*=== Corporadon (USEC or the Cwyvs. des) submined Revision 1 of the CW-Plan for the Pascah Gaseous Diffusion Plant (PGDP) to it.e Unhed Semes Nt: clear Reguissory ca=====aa (NRC) Revision 1 of the Ca==H= Plan, which had been approved earlier by ibe U.S. Deparunant of Energy (DOE), was mdwaarad as a part of Revision 1 to the USEC applicanon for an kudal certificate of compliance (hereafter 4

referred to as the Application)in accordance with Section 1701(c) of the Monde Energy Act of l

1954 (AEA), as amended, and Part 76, "Corrinemiaa of Gaa=== Diffhsion Plants,* of Thie 10 of the Code of Federal Regulanons (10 CFR 76). Section 76.35(b) of 10 CFR requires that the Application inchade the following:

A plan prepared and approved by DOE for achieving ra"T'i""* wish respect to any arass of -

-.' = wida NRC's regalances that are Wennfled by the Corporation as of the dars of appbconan that includes:

(1) A dancripnan of the arose of anacompliance; (2) A plan of acocos and s mdales for.shitving E--,9 =; and (3) A)=ri% for continued opersnan whh adequais safety and safeguards.

The regulations assign to the Cei vision the respoossility for id Wieg to DOE the y

noncompliances to be addresand in the plan for achieving _--5"==. The DOE-prepared Compliance Plan inchadas (1) danaiptions of tbs areas of --- -..i =, (2)f=rineariaan for canr===d operation, wtuch dese:te the provisions to emure adequese asfery and safegua the idenrined areas of W" are being alimiamai, and (3) plans of actions and achedules for achievmg complian:e in these armes. Became many parts of 10 CFR 76 and sections of cisv durvin are perfonnance based, only the NRC can deannine whether the ea==inna== m by USEC are adequate to meet the regarements. DOE has not amepend to evalusse the a of 9......... -. made in the USEC A,5"

?-w. Hoover, DOE has indap=damly conadered 4

whether PGDP mi have impismsmed the programs and yh and instaDad the required equipment to fu:fE1 the cor%nents smand in the revised Applicsion. Where the c programs, procedures, and egepamat differ frtun the commtuness, the nonconformanca addressed in this Compliance Plan, whether or not ths.y eaa=name devisions freen applicab reguladons.

Revision 1 of the DOE-approved Compliance Plan addressed thoes aspeca of the operati at PGDP that were Idamined by USEC in Revision 1 of its Application as not curready be i

full ca=plinara with enher the applicabit NRC requirements or the.

J-.. - ast fbrth in the Revision 2 of the DOE-approved ca r-Plan, encampensing Revuions USEC A;=8ia-iaa 2,2A, and 2B, addressed (1) those aspeca of the operanons at PGDP that were idan USEC in Revision 2 of its Application as not

.,4 being in fuD compliance with either the applicable NRC requiresnents or the eaa======= est forth in the USEC Application and (2) cr==aianaare made to modify the Ca-n a* Plan in temponse e NRC quesdons on the Revision 1 USEC Ag" ='-w and the Revison 1 DOE CP Plan. DOS has prepared and approved i

this revision to the Complian:e Plan e address (1) au PGDP noncomphances identined

'a im Revision 3 Application and its responses to NRC quesnons through July 9,1996, any new Ca="- Plan issues not identifled in the USEC Revision 3 A',-Ha~iaa. a c

aa==i===== made to modify she Revision 2 Cg" = Plan in the responses to NRC questions regarding Revision 1 and 2 of the PGDP Compliance Plan.

PGDP Rsv. 3,7886 e

..=-a.

xxx The am of the noncompliances described in this plan does not 'vilcare a diffmace in i

the overall level of health, safery, and safeguards praecuon provided to workers and the public under DOE and NRC oversight. Rather, these nonccampliances resect (1) areas where compliance has not yet been achieved to exstag DOE requuunents or (2) diffences between the NRC and DOE regulsory approaches to asure adequae prosection of the health and safety of workers and the public and to protnam the tenanon defense and securny. DOE omraight has generally been e

frorn the penpecave of a L."; 4 owner-opsamr, wth gamer emphasis upon pancriv ve requininses and mon direct hvolvensa in facilky operuions. NRC, as an independant regnismry agency emP oying performame oriened ruins, quke nanually requires mm formal l

h and gresser fonnalky in operating practicas to prcmde -.... ~

asemance of adequese safety and safeguards.

(

In preparing the C=ah Plan, DOE has reviewed the past operating himony of the plant as evidenced by ase=r= '=, andhs, reviews, evem reporu, and DOE Regulatory Chersight i

Program inspections. Where past evens indicae that USEC is not in full conformance with the programs, procedures, and eqmpment needed for ' ; * -- -

L=- of the cr==nianar= sized in the revned App!! %, mch noncomplianca are also addressed in this Compliance Plan. DOE has also daarminar that the completion of the plans of actic 2 and schedules== lined in the Compliance Plan will address the deSciencies idenrad frcan past er.a.

Thus, DOE approval of the Compliance Plan is based, in part, upon is canchi=ian that For the noncompliances id==hd by the Cwmds, the upgrades propoed in the plans of

~

acsion will, when completed, bring PGDP into c

"== with the -....J... -. In tb Application.

The panne=rians for caar===i operation presented in t by DOE to be -~~*=ble for assurms @*- anfery and safeguards, F

~ -s-The plans of actions and =4=hlas for the klanrad noncompliances represent an appropriate g g 3 means cef bringing PGDP kno c--f':=e with the -.....o... -. in the revhrd App 39~iaa -< p $

as rapidly as can be safely and effecovely managed. Purthermore, se priority afforded pgp n-individual uP5rade actions is, to the..

s..... extent peiaakle, crunmanerate witt: the

h safety or safeguards riak associated with the noncompliance.

p,l [

If e

in several inernacea, USEC has reported that the plans of actions to eliminate an ident&d e

c noncompliance have been completed. Thur, thsee issnes are no longer USEC-idenn6ed t[

noncompliances and the -.....:.... - made in their >=aar=ia== for ennismed operadon are yp I

=r== dad by the W+=' of the canapandag Applicsion egegknumm. Innes, belmiing 7g5 ihejusencadons for==i==4 operadon, the have besa P %::.

7 = F-7yF

,, --I h 91

', a P 20 ^

s =0 -

..g -

f

a.-
]$

'- - f h t C _ _, " -- Pluned i ' = *:

f t ;'

Of Id hi r t '-t:::

'l " kj ^^ = 0 0,=

,,,.1

,t' 6. f 1:

i g

rt': ef :

O t x1' * ^ t ' ; - h;.

eL

.W l

hhamspia v to the Of5ce of Nadear Material Safety and Safeguards (NMSS) Director's

s.,

decision cm innial certification, USEC will provide quarterly reports a NRC on the imple==enrinn g- -

stams of Compliance Plan =nminnants-These v h status repors will include, where appropriam, proposed revisions ao remove ?; - _ _ -

M ef x -_:

."---- that have been l $ We 1 o

i i

f gemph.M Ocm b.(cmph w t hoo xxu j

cleses. The reports will dso inchnic an execunve ennmary that idennfles plans of acdons that were completed durms the par Juartsr plam of acnons scheduled to compimed durmg the next 4

i quarter, anri a discussion of any plans of actions that m behind schedule. The execunve summary will be supported by a detailed listag, sorted by noncompliance, of the indivkhtal -.....J within each plan of accons. The listag will include a compamon of the er===in==nr completion detr. with the current projected canplenan date for each indiviskaal

-.J-. - that has not been I

coupissed. The first such report will be provuled to NRC no later than 90 Sys after the NMSS Direczor's decision on insial certificaten. These reports will be provided until either all plans of I

acxions in the PGDP CW-Plan have been compissed or the NRC agress that the reports a:e i

no longer necessary.

J In addition to the......'...... made in the AppIWdaa USEC has made -..~.'~.

relatmg to nuclear safety and safeguards, to DOE under tin DOE regulamry oversight program.

To ensure that nc UShC c inn =na to ade operanon are lost in the transition of regulatory ovmight from DOE to NRC, DOE will prtrAde to NRC: (1) a listag of all open regulatory

, m..@ inspection items affectag PGDP, Wu references to anppornas in=parnaa repom 1

or cm.g ===, G) copies of draft PGDP regulatory oversight inspecnon reports aniting issuance on the regulatory oversight transition date (3) annmanes of the findings and concerns j

idermined dunng any in=parmar= frir wtuch draft s a=% repom had not been wrsten as of the a

regulatory tran==ian date, and (4 a listag of all open USEC.>.,. '- - affecung PGDP that f

were made in response to regula:ory oversight inspections, modifications to the Regulatory Cw.;ght A,s s, or other regulatory oversight activmes, including reference to supporting

~

inap-aan reports or correspondence. These listmas of open regulatory oversight issues and e,==nawwna, the draft regulatory oversigin inspection repom, and the insperian findings

==nmanes will be prended to NRC by DOE withm the week after NRC assumes responsibilny for regulatory oversight of PGDP.

This Compliance Plan roughly paraDels the structure of the ApalWdan wah the compliance issues y.

s.d in approrimately the sane order as the most :WW== of the -

~ -

addressed by each issue.1be A=al%= describes aspects of the operations at PGDP as they will be when PGDP is in full comphance. In those cases where some aspect of the operanon is not My in full compliance with applicable NRC regulations, the naner=nplianr* is descrhed in the Applicanon and in this Compliance Plan, as required by 10 CPR 76.35(b)(1). In the intmst of simplicity and clarsy, sevual of the indivichal Compliance Plan issues address uninple specific noncomphances idanan=d ta the Aw-aaa As an aid to the reviewers, the Imkages between the Compliance Plan issues and the naaerwnpliances cited in the Application are shown in a table the front of this h To aid in locanns the eaa=H=aea issues, this daennwar also includes a table relaang each compliance inue to the correspondmg NRC regulations and to the sectiors of the Application that contam the.. 2- - referenced.n the compliance imme, in sotne of the compliance issues, the plaaned acuous described include operational enhanesmansa that are not, in the judgment of DOE, necessary to meet the applicable NRC requuunents. Such operational enhane===na are not the financial responsibility of DOE und the 1.anse Agreement between DOE and USBC. These operational enhanceme.un, which generaDy

)

m relased in acxivines required e achieve ~==anmith the NRC requiranents, m docused in this plan solely to provide a mort :---- " description of the proposed upgrades. The c.Pa luuss for which the planned actions include this type of opersional anhantwnware m idenrin ci in the r6ie of Coatsats by an astersk at the end of the issue title.

PGDP Rev. 3. 7896

~..

4 a

xxxii j

in compliance wkh 10 CFR 76.33(e), those ponions of the Compliance Plan that enranin wkhboidable infonnsdon have been placed in the A,e p infonnarion includes Rasticsed Dam, Nadonal securky Infonannon, safeguards Infann= nan Unclassised Connolled Nacirr Infonandon, proprisery dem, and ashst such infonandon. Where wahholdable infonnadan is rmfiired to describe a ar=w-pilaar*, justify tw=rir==d operadon, or present planned acdous and schechdse that would othennes be in the body of the c4 ~ Plan, the compliance issue is discussed in the Ae x

The Compliance Phm discamion begins by rekuncing the muinary requiransat and remnang or=== n=rming em %% met -.

.. - fnna tum 1b discusion condanes whh the soBowing:

descripdon of the speciSc ares (s) of w+ -- ^ = [per 10 CFR 76.35(bX1)),

i a : *= for r====d opersdon wkh adeques afery and safogands

[per 10 CFR 76.35(bX3)], and planned actions and Mlas for achieving caiglianra [per 10 CPR 76.35(bX2))

This diaen-ina ir foBoww! wth a table the links the Cargliance Plan imus widi (1) the applicable regulasory 'equiremsass, (2) the relevant aan=ninn== m fnun de AWh. and (3) the noncompliance== -=r== lissed in the Applicadon that are addnesed by the CW Plan

issue, in sommary, the Comphume Plan conmins the kdonnscian regered by 10 CPR 76.35(b) and has bus papered and approved by DOE, as indicased by the signsors on the approvals page.

i I

l l

l t

i s/

l E G ilsv 317/996

harkupi/aQu DOE /ORO 2027/R3 l

Plan for Achieving Compliance with NRC Regulations at the Portsmouth Gaseous Diffusion Plant i

July 9,1996 b

Prepared by DOE Compliance Plan Project Team Trepared for 1

U.S. bepartmets of Energy J

Oak Rkige Operations Oak Ridge, Te-aw 37830

~

111

.~

CONTENTS Eage PORTS COMPLIANCE PLAN ISSUES AND NONCOMPLIANCES CITED IN THE APPLIC ATION....................................... v PORTS MATRIX OF COMPLIANCE ISSUES 10 CFR REQUIREMENTS, AND APPLICATION DOCUMENTS............................

ix AB B REVIATIONS............................................... xxi l

G LOSS AR Y.................................................. xxv l

INTRO D UCTION............................................... xxix l

COMPLIANCE PLAN ISSUES Issue Transivon frem DOE Regulation to NRC Regulation (Ccropit7td)............

1 Update the Application Safety Analysis Report'

...................2 l

Autoclave Upgrades *

................................3 l

X 705 Evaporator Heat Exchanger Modificationst.(.cenp.lrtecl.)............. 4 X 705 Isolation Valve Testingt (completed)..........................5 l

l X.705 Microfiltratica Influent pH Shutdown System Replacement *t (completed)... 6 l

HEPA l-liter Systems Testing *.(.ccmpleted.)...........,............ 7 l

Nuclear Criticality Safety Approval Documents.(.ccmpktcd ).....,.......... 8 Nuclear Criticality Safety Approval Implementation.(. temp dtd.1....,....... 9 j

Nuclear Criticality Safety Training for Managerst (completed)..............

10 l

Exceptions for Criticality Accident Alarm System........................ I1 Radiation Protection Procedures (C Mp k.te d.).,,.................... 12 l

Posting of Radioactive Materials

  • 13 l

l NVLAP Certification * (completed)................................ 14 Fire Protection Compensatory Measurest (completed)

..,................15 Fire Protection Sprinkler Testing *t

.........................16 l

Fire Protection Procedures and Hot Work Permit Program................

17 l

Emergency Packetst (cce pided.)..............................

18

  • These issues may not be fully.eimbursable by the U.S. Department of Energy.

tThese issues are ursque to the PORTS facility.

PORTS Rev. 3. 7/9/96 y

iv l

Packaging and Transportation (completed)...........................

19 l

DOE Chemical Safety and Third. Party Use of Havidous Chemicals * (C.ompk. fed ).

20 Management Controls.........................................

21 Safety Committees (.Cornp.It.f ed.)................................22 Plant Changes and Configuration Management.........................

23 Mainte nance Program.........................................

24 Operations Program. ( cmp lde d.)...............................

25 -

Systems Approach to Trwaing....................................

26 Ae-ntst (.CWM ul)....................................

27 Event Investigations ux! Reporting Program.(.Ctaple.ttd.)...,...........

28 Records Management and Document Control Program....................

29 Proc edures Program *..........................................

30 l

Q List (del ted)......................

31 Quality Assurance Program Irnplementation................,.........

32 l

Emergency Plan Support Documents (completed)......,...............

33 Training for Emergerry Preparednesst (Ccmplt.ttd.)...................

34 Quality Control Program for Low. Level Waste Disposal (completed)..........

35 Depleted Uranium Management Plan * (Cunplc7td)...................

36

~

l Administrative Controls on Overtime *.(.complate d).....................

37 l

Decor'..missioning Funding Program;

..............................38 l

Chemical Safety Mechanical Integrity Program

  • k/h...............

39

~

l l

Operational /S.fety System Trip R,edundancy (=ccapMu$..................

40

~

l Codes and stareards (#tsh)................................

41 l

UF. Leak Detector Sensitivity Testing * (

,,,..................42 l

10 CFR 21 Implementing Procedures (deleted)...........,............

43 l

Criticality Accidetu Alarms for Nearby Buildings (new issue)...............

44

'These issues may net be fully reimbursable by the U.S. Department of Energy, tibese issues are unique to the PORTS facility.

l (The U.S. Department of Energy has no financial obligation related to this issue.

PORTS Rev,3. 7/9.96 ir I

m

v PORTS Compliance Plan Issues and Noncompliances Cited in the Application Issue (Number)

Area Where Identifled in Application Transition from uve-iirgulatio.e^ Wc Nnt id- &d by i.jsec

~

Regulation (D Update the Application Safety Analysis Report i PORTS SAR 2.7 (2)

PORTS SAR 3.9.1 l

Autoclave Upgrades (3)

PORTS SAR 3.9.2, 3.9.6, 3.9.9 l

h 05 Evnporator Heat Exchanger PORTS SAR 3.9.3 l

M cations (4)

X 705 Iskoon Valve Tes+1ng (5)

PORTS SAR 3.9.3

[

l X 705 Microfi'ltMion influent pil Shutdown PORTS SAR 3.9.3 l

System Replacemehq6) llEPA tilter Systems TMg (7)

PORTS SAR S d f

\\

PORTS SA,R 5.3.7.4 Nuclear Criticality Safety ApproDat ocuments POR'LfSAR 5.2.4.1 (8)

PpRTS SAR 5.2.4.2

,. ON PORTS SAR 5.2.4.6 PORTS SAR 5.2.4.9 PORTS SAR 5.2.4.10 TS SAR 5.2.4.11 Nuclear Criticality Safety Approv PORThSAR 5.2.4.1 Implementation (9)

PORTS SQS.2.4.2 PORTS SAR N.4.3 PORTS SAR 5.2N4 PORTS SAR 5.2.4.5 PORTS SAR 5.2.4.7 PORTS SAR 5 2.4.11 PORTS SAR 5.2.4.I'2 Nu ar Criticality Safety Training for PORTS SAR 5.2.4.3 h.

anagers (10)

\\

Exceptions for Criticality Accident Aarm PORTS SAR 5.2.4.8 System (11)

Radiation PforetthnrProcedatull2)

PORTS S PORTS Posting of Radioactive Materials (13)

PORTS SAR 5.3.7.2

__M N

\\.

NVLAP Certific'IttetrtH)

Fire PatectionbrcWMeasures (15)

PORTS SAR 3.4.o PORTS Rev. 3. 7/9/96

vi PORTS Compliance Plan Issues and Noncompliances Cited in the Application (continued)

Issue (Number)

Area Where Identified in Application F!re Protection Spridin Tn: ce; TOan E^? 5 4 A Fire Protection Procedures (17)

PORTS SAR 5:4.8 Em PackstQ18)

PORTS SAR 5.4.8 Packaging and Transportatio M S.1 DOE Chemical

" LMUse of PORTS Ha cals (20)

Management Controls (21)

PORTS SAR 6.1.3 l

PORTS QAP Appendix B-1.0 (item 1)

Safety Committees (u; PODTS !'" '. 5 Ms 36 i-k3 i

Flant Changes and Configuranon Management PC ATS SAR 6.3.6.1 l

(23)

PORTS SAR 6.3.6.2 l

PORTS SAR 6.3.6.3 PORTS SAR 6.3.6.4 PORTS SAR 6.3.6.5 l

PORTS SAR 6.3.6.6 Maintenance Program (24)

PORTS SAR 6.4.13.1 PORTS SAR 6.4.13.2 PORTS SAR 6,4.13.3 PORTS SAR 6.4.13.4 i

PORTS SAR 6.4.13.5 I

Operations Program (dj PODTMAR 6.3.iu.1 POR15s d 0.'.l0.2 l

Systems Approach to Traits 1(26)

PORTS SAR 6.6.22.1,6.6.22.2 PORTS S

~

E gam Records Managem*nt and Document Control PORTS SAR 6.10.5.1 Program (29)

PORTS QAP Appendix B-1.0, items 1 and 3 Procedures Program (30)

PORTS SAR 5.7.5 PORTS SAR 6.11.8.1 PORTS SAR 6.11.8.2 PORTS SAR 6.11.8.3 l

PORTS SAR 6.11.8.4 PORTS Rev. 3,7/9/96 o

vil PORTS Compliance Plan Issues and Noncompliances Cited in the Application (continued)

Issue (Number)

Area Where Identified in Application Q Li5s1) (deletedL_._

l-Quality Assurance Program implementation PORTS QAP Appendix B l

(32) lan Support Documents (33)

PORTS Emergency Plan Appe Training for Emerg eparedness (34)

PORTS Emerge Appendix E, l

7.2.1,7'

,.2.3 Quality Control Program for Low Level W

'RTS RWMP 7 Disposal (35)

Depleted Uram ent Plan (36)

Not identified e Controls on Overtime (37)

PORTS SAR 6.5.10.3

\\

l Decommissioning Funding Propun (38)

Not Identified by USEC Chem.

fety MechanicalIntegrity Program i PORTS SAR 5.6.15 (39)

Operational / Safety System Trip Re 3 9.4 (40)

Codes and Standardsf41[

PORTS A

l U

tor Sensitivity T+ sting (42)

PORTS SAR 3.9.5 l

10 CFR e

/ deleted) l Criticality Accident Alarm System-Slaved PORTS SAR 3.9.7 Buildings (44)

M PORTS Rev. 3,7/9/96

-~

_ - -. ~ -. -.

ix PORTS Matrix of Compliance issues,10 CFR Requirements, and Application Documents 1

10 CFR Requirernent Application Doctanent (Section)

Issue Title (Number) 76.5 Analysis Report T.M Regulation to NRC (6.1.1

~

WEW 76.35(a)(4), (6), and (8);

Safety Analysis Repon Update the Applicadon 76.85 (2, 3, 4)

Safety Analysis Report (2) 76.35(a)(6),76.85, Safety Analysis Repon (3.2.1.1, Autoclave Upgrades (3) 76.87(c)(5) 3.2.1.2, 3.2.1.3, 3.4.4.4, 4.2.3)

Techniut! Safety Requirements (2.1)

.35(a)(6), 76.85, Safety Analysis Report X-705 Evaporator He

76. (c)(3)

(3.3.1.4.10)

Exchanger Modifi ons 2

(4) 76.35(a)(6), "6.85, Safety Analysis Repon X 705 Isolarfo'n Valve 76.87(c)(3 (3.3.1.5.2, 3.3.2.1.2.6)

Testing Technical Safety Requirements (2.6.3.1, 2.6.3.2, 2.6.3.3, 2.6.3.6)

~

76.35(h)(6), 76.85, fety Analysis Repon (3.3.2.1,2 X 705 Microfiltration 76.87(c)(3)

Influent pH Shutdown Tec Safety Requireme System Replacement (6)

(2.6.2,2. 3.5) 20.1101(a) and (b),

Safety Analys}Nte (5.1, 5.3)

HEPA Filter Systems l

20.1701, 76.60(d),

Testing (7) 76.87(c)(5) 76.35(a)(5), (6), and (7);

Safety A ysis Repon (. 2.3)

Nuclear Crideality 76.85; 76.87(c)(3)

Safety Approval Te

' cal Safety Requirements Documents (8)

.9.1.c, 3.11) l 76.35(a)(5), (6), and (

Safety Analysis Repon (5.2.2.3, clear Criticality 76.87(c)(3); 76 (ge al) 5.2.2.6, 5.2.2.7, 5.2.2.8, 5.2.2.9, S

Approval 6.9)

Implernentation (9)

Technical Safety Requirements (3.9.1.c, 3.11)

C;uality Assurance Program C

(Appendix A-Section 1)

PORTS Rev. 3. 7/9/96

~_

K PORTS Matrix of Compliance Issues,10 CFR Requk

, and Application Documents (continued) 10 CFR Requirunent Application Docenent (Section)

Issue Title (Number)

Y Safety Analysis Repen Nuci i

' ' 5.2.4.3) afety Training for

~~

Managers (10) 4 (3.3,3,30 76.89(a)

Safety Analysis Report Exceptions for Criticality (5.2.2.5)

Accident Alarm System i

(11)

Technical Safety Requirements (2.1.3.1, 2.2.3.2, 2.4.3.1, 2.5.3.1, 2.6.3.4, 2.7.3.2, 2.8.3.1) 2 Safety Analysis Reoort Radia '

ion 76.60(d)(2)

.3. 5.0.1.5) ocedures (12) cal Safety Require 20.1501(a)(2)(iii),

Safety Analysis Report I osting of Radioactive 20.1902, 20.1904(a),

(5.3.1.7)

Materials (13) 76.60(d)(2)

Technica! Safety Requirements (3.13) 20.

)(2),

Safety Analysis Report NVLAP Certifi 20.1501(c),

d)(2)

(5.3.2.4)

(14) a1 Safety Requirements (3.13) 76.87(c)(4)

Safety epo Fire Protection (5.

,5.4.7)

Compensatory Measures

/

R 76.87(c)

Safety Analysis Report Fire Protec '

S rinkler (J.4.4)

Testing (16) 76.87(c)(4)

Safety Analysis Report Fire Protection (5.4.1, 5.4.1.1, 5.4.1.2, 5.4.2, Procedures (17) 5.4.4, 5.4.6.3) 7D4 Safety Analysis Report N)

~

~

M Repo ej 76.60(g

)-

PORTS Rev. 3,7/9/96

xi PORTS Matrix of Compliance Issues,10 CFR Requirements, and Application Documents (continued) 10 CFR Requirunent Application Document (Section) lasue Title (Number)

D

,76.87(c)(11)

Safety Analysis Report (5.614)

DOE Chemical and Use of Technical Safety Requirements dous hie =le D8r3J3)

(20)

Emergenc

.9, 2.2.2, 1

2 ',

1, 7.2, 7.5, 7.6, 8, Quality Assurance Program (Appendix A)

\\

76.35(a)(3),76.35(a)(7),

Safety Analysis Report Management Controls 76.93 (3.7.2, 4.1.1.3.1, 4.5.1.2, 4.5.7, (21)

I 5.1,

.J.2, 5.3, 5 J 1, 5 6.1, 5.7.1, 6.1, 6..! 6.3, 6.4, 6.5, 6.6, 6.7, 6.8,19, 6.10, 6.11: Chapter

(

4-Appendix C, C.I.2.2.2).

Technical Safety Requirements (3.0)

Fundamental Nuclear Materials Control Plan (2,3,5.1)

Emergency Plan (4.1,4.2,9.2)

Radioactive Waste Management (1)

Physical Security Plan for the Transportation of Special Nuclear Material of Low Strategic Significance (2.3,2.4,4)

Quality Assurance Program (2.1, 2.2)

Security Plan for the Protection of Classified Matter (Classified)

Depleted Uranium Management Plan '

(1.0)

( ' '.

Decommissioning Funding Program (2.0)

PORTS Rev. 3,7/9/96 j

xil m

PORTS Matrix of Compliance Issues,10 CFR Requirements, and Application Documents (continued) 10 CFR Requiranent Applicadon Document (Section)

Issue Title (Number)

"6.

,76.68(a)(2)

Safety Analysis Report Safety CommWd (5.1.1, 5.2.2.2, 5.2.2.3, 5.2.2.8,

.3.1.2, 5.3.1.3, 5.4.1, 5.6.M.3, 5

6...,

6.3.1, 6.3.2, 6.3 6.3.5.2.3,.

.8.2, 6.9.6, 6.1

.1..

.11.4.6,

,6,thft4)

  • Technical Safety Requirements (3.10) 76.35(a)(4) and (6),

Saf;ty Analysis Report Plant Changes and 76.51, 76.68, 76.85, (5.2.2.4, 5.2.2.6, 5.2.2.8, 5.4.6.2, Configuration 76.87(a), 76.87(c),

5.6.6, 6.1.1.18, 6.2, 6.3, 6.4, 6.5, Management (23) 76.93, 76.95 6.6, 6.7, 6.8, 6.10, 6.11)

Quality Assurance Program (2.3, 2.4, 2.6, 2.7, 2.8, 2.9, 2.10, 2.11, 2.13, 2.15, 2.17, Appendix

~

A-2.3, 2.4, 2.6, 2.7, 2.8, 2 9, 2.10, 2.11, 2.13, 2.15, 2.17) 76.87(c)(7)

Safety Analysis Report (3.5.1,5.3.5, Maintenance Program 5.6.5, 5.6.5.1, 5.6.5.2, 5.6.5.3, (24)

1, 5.7.3.2, 5.7.3.4, 5.7.3.5, t,. ^ *

  • 1.1.9, 6.1.1.11, 6.1.1.14, 6.1.1.2v, 6.1.1.25, 6.3.5.2.3.6, 6.3.5.2.4.2, 6.3.5.4.2, 6.3.5.6, 6.3.5.7, 6.4, 6.5.7, 6.6.1, 6.6.3, 6.6.3.1, 6.6.5, 6.6.13, 6.8.2.2, 6.8.2.3, 6.8.2.4, 6.10.1.13, 6.11.1, 6.11.5,6.11-Appendix A)

Technical Safety Requirements (3.2.2.b, 3.9.1, 3.15, 3.24)

Furvhmental Nuclear Materials Control Plan (2.2.7, 2.6, 4.1, 4.1.1, 5.1.2, 5.2, 5.2.1, 5.2.3, 13.1)

Emergency Plan (4.LU, 7.6, 8.2)

Quality Assurance Program (1-2,18, Appendix A)

PORTS Rev. 3. 7/9/96

i xiii PORTS Matrix of Compliance Inues,10 CFR Requirements, and Application Documents (continues, 10 CFR Requirement Application Document (Section)

Imue Thie Mumber) 7 Safety Analysis Report (6.3) 5)

76.87(c)(14),76.87(d)(6)

(1.19) 19,20, 76.35(a)(5),

Safety Analysis Report Systems Approach to 76.60, 76.87(c),

(6.6, 6.6.1, 6.6.3)

Training (26) 76.91(j),76.95 Quality Assurance Program (2.2.4)

Technical Safety Requirements (3.4) 35(a)(7)

Safety Analysis Report Assessments (27)

(5.2.2.9, 5.6.9, 6.3 5.1, 6.3.5.6, 6.8, 6.8.2, 6.10.1. t 5)

Fundamental Nuclear Materials Control Plan (10.1)

Technical Safety Requirements (3.5) 76.35(a)(7),76.60, kafety Analysis Report Event Investigations and 76.119, 76.120 (5'. 2.2, 5.3.4.2, 5.6.8, 6.1.1.1,

Reporting Program (28) 6.5.1,

.7. 6.9)

Technical ety Requ' ents (3.10.5.h, 3.1 3.1 -

Fuuhmeel

-let aterials Control P (1.4,1.5, 6, 1.7, 8.6, 9.,

.4,12.5) rgency Plan

.2.1, 3.2.2, 3.3, 4.1.14)

Security Plan for the Protection of Classified Matter (Classified)

Physical Security Plan for the Transportation of Special Nuclear Material of 1.ow Strategic Significance (7.3.1, 7.3.2, 8.3, 9.,

t 10.3, 10.4, 11)

PORTS Rev. 3,7/9/96

XIV PORTS Matrix of Counpliance Imues,10 CFR Requir==te, and Application Documents (continued) 10 CFR Requiruneet Application Document (Section)

Issue Title (Nanber) 76.35(a)(7),7J.93 Safety Analysis Report Records Management (3.5.5.1, 3.5.5.4, 5.1.2.7. 5.2.2.3, and Document Control l

5.2.2.6, 5.2.2.8, 5.2.3.2, 5.3.1.2, Program (29) 5.3.1.3, 5.3.1.5, 5.3.1.6, 5.3.1.7, 5.3.2.10, 5.3.4.2, 5.3.5, 5.3.6, 5.4.8, 5.6.3, 5.6.3.1, 5.6.13, 5.6.13.3, 5.7.3.2, 5.7.3.4, 5.7.3.7, 6.2, 6.3.1, 6.3.2, 6.3.3, 6.3.4, 6.3.5.2.3.2.e, 6.3.5.2.3.4, 6.3.5.2.3.6 a, 6.3.5.2.3.8, 6.3.5.4, 6.3.5.5, 6.4.5, 6.4.7. 6.4.8, 6.4.11, 6.4.12.1, 6.4.12.2, 6.5.5, 6.5.5.2, 6.5.6, 6.6.2, 6.6.3.1, 6.6.21, 6.9.4, 6.9.6, 6.10.1, 6.10.2, 6.10

  • 2 6.11.1, 6.11.4.7, 6.11.4.8, 6.14.5, 6.11.6, 6.11.7)

Technical Safety Requirements (3.6, 3.9, 3.10.6, 3.24)

Physical Security Plan for the Transportation of Special Nuclear Material of1.ow Strategic Significance (4.2, S., 5.4.1, 5.4.2, 10.,10.1, Addendum 1-5.1.2, 7.3.9,8.2.2, Addendum 2-5.4.10, 6.2.1.F. 7.0)

Fundamental Nuclear Materials Control Plan (1.7, 2.3, 2.4, 2.5, 3.,

4., 5.1.2, 5.2, 8.3, 9.4, 10.2, 12.1, 12.4, 13.1, 13.2)

Emergency Plan (4.1.9, 7.1,7.2, 7.7, 8.1, 8.2, 9.2)

(continued on nextpage) v l

l.

PORTS Rev. 3. 7/9,96 N

xv s

PORTS Matrix of Compliance Issues,10 CFR Requirenents, and Application Donunents (continued) le CFR Requirunent Application Decat (Section)

Issue Title (Number) l (continuedfrompreviouspage)

Quality Assurance Program (2.2.2, 2.2.4, 2.3.1, 2.3.3.1, 2.3.3.3, 2.3.3.5, 2.3.3.6, 2.3.3.7, 2.4.1, 2.4.3.1, 2.4.3.3, 2.5.1, 2.6, 2.7.3.2, 2.7.3.5, 2.7.3.8, 2.7.3.9, 2.8.3.4, 2.9.3.3, 2.10.3.11, 2.11.3.1.4, 2.11 3.2, 2.12.3, 2.15.3.8, 2.17, 2.18.3.8: Appendix A. Sections 1-1.2, t.3,1.4,1.5,1.6,1.7,1.8, 1.9.1.10,1.11,1.12,1.15,1.17, 1.18, 2-2.2, 2.3, 2.4, 2.5, 2.6, 2.7, 2.8, 2.9, 2.10, 2.1. 2.12, 2.15, 2.17, 2.18, 3-3.2; Appendix C)

Security Plan for the Retention of Classified Matter (Classified)

,.s Decommissioning Funding Program (4.0)

Depleted Uranium Management Plan (3.0)

Radioactive Waste Management Program (6.6, 6.7)

'. j PORTS Rev. 3,7/9/96

xvi PORTS Matrix of Canpliance Issues,10 CFR Requireen*=es, and Application D<w,anana (continued) le CFR Requirunent Application Document (Sectice)

Issue Title (Number) 76.10(c),76.35(a)(7),

Fafety Analysis RLport-Procedures Program (30) 76.35(k),76.60(c)(i),

(4.2.2.2, 4.2.2.5, 4.2.2.6, 4.2.2.7, 76.68(c), 76.85, 4.2.2.15, 4.2.3, 4.2.3.1, 4.3.1.2, 76.87(c) and (d),

4.3.1.3, 4.3.1.4, 4.3.2.2, 4.3.4.1, 76.91(j),76.93 4.4.7.1, 4.4.7.3, 4.5.1, 4.5.1.5, 4.5.2, 4.5.2.1, 4.5.2.4, 4.6.1.6, 4.6.1.7, 4.6.1.10, 5.1.1.1, 5.1.1.2, 5.2.1, 5.2.2, 5.2.2.2, 5.2.2.3, 5.2.2.6, 5.2.2.7. 5.2.2.8, 5.3.1.1, 5.3.1.3, 5.3.1.5, 5.3.2.1, 5.3.2.2, 5.3.2.6, 5.3.2.8, 5.3.3.1, 5.3.3.2, 5.3.4.1, 5.3.4.2, 5.4.1, 5.4.4, 5.4.7, 5.5, 5.6.3, 5.6.3.1, 5.6.5.2, 5.6.9, 5.6.13.4, * .3, 5.7.3., 5.7.3 4, 5.7.3.6, 5.7.3.7, 6.1.2, 6.2, 6.3.2, 6.3.3.2, 6.3.5.1.1, 6.3.5.2.1, 6.3.5.2.3, 6.3.5.4.1, 6.4.5, 6.5.5, 6.6.1, 6.6.3.5, 6.7.1, 6.8,6.9. 6.10, 6.11)

Technical Safety Requirements (3.9, 3.10)

Emergency Plan (7.1,7.5)

Quality Assurance Program (2.2, 2.3, 2.4, 2.5, 2.6, 2.7, 2.8, 2.9, 2.10, 2.11, 2.12, 2.13, 2.14, 2.15, 2.16, 2.17, 2.18, Appendix A)

Radioactive Wasa Management Program (7)

Depleted Uranium Management Plan (3.0)

Q4:tstT3T)

~

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'~s PORTS Rev. 3. 7/9/96 o

xvil PORTS Matnx of Compliance issues,10 CFR Requirements, and Application Documents (cont;nued) 10 CFR Requirement Application Document (Section)

Issue Title (Number) 76.93 Safety Analysis Repe Quality Assurance (6.4, 6.8)

Program Implementation (32)

Quality Assurance Progran (1-2.18, Appendixes A and C)

Technical Safety Requirements (3y 91(m)

Emergency Plan aergency Plan Sup (Plan Summmy,7.1,10 socuments (33) 76.91(j)

Emergency Plan Training for ergency (7.2.1, 7.2.2, 7.2.3)

Preparedne (34) 76.00(d)(2),20.2 (d),

TMn-uuy Requirements Quali ontrol Program Appendix F to Pan (3.14) for ow-Level Waste 90 sal (35) dioactive Waste Management j

P am (6.5)

/

76 A,76.35(m)

Safetyhlysis Report Depleted Uranium (3.2, 3.2.3 3.2.7, 4.2.1, 3,

Management Flan (36) g 4.2.3.1, 4.2. ', 4.2.3 2)

~

Technical Safety irements (2.5)

Er.:rgenc7 dan (1.1,2.

,2.2.2)

Dep ed Uranium Managemen Ian

, 2.0, 3.0)

/

Decommissioning Funding Program (1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 4.0, 5.0, 6.0) 76.35(e) 7 7(d)(6)

Safety Analysis Report Admuustrah Grtrols (6.5.10.3) on Ovenime (3 Technical Safety Requirements (3.2.2.b)

PORTS Rev. 3,7/9/96

tviil PORTS Matrix of Compliance Issues,10 CFR Requirements, and Application Documents (continued) 10 CFR Requirement Application Document (Section)

Issue Title (Number) 76.35(m), 76.35(n),

Safety Analysis Report (6.3.3.2)

Decommissioning 76.83(a), 76.83(b),

Funding Program (38) 76.83(c)

Technical Safety Requirements (2.2.3.16, 2.7.3.15, 3.14)

Radioactive Waste Management Program (3, 4, 5.1, 5.2, 5.3, 5.4, 6.1,6.2,6.3,6.4,6.5,6.6,67)

Depleted Uranium Management Y l

(1.0, 2.0, 3.0)

Decommissioning Funding i togram (1.^, 2.0, 3.0, 3. ' 3.2, 3.3 4.0 5.0, 6.0) 6),76.37(c)(11)

Safety Analysis Report Chemical Safety (5.6.1, 5.6.5. 5.6.13.3. 6.4) hiechanical grity

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Technical Safety Requirements 5, 3.18)

Emergency 2.1 1.9,2.2.2, 22.3,7.1,72 6, 8, 10)

Assurance Program (2..

y Appendix A-1.12,2.10,2.12)

N 76.120(c)(2)

Safety Analysis Report (6.9)

Operatio Safety System Trip R

$cy (40)

N c

PORTS Rev. 3. 7/9/96

,a

xix PORTS Matrix of Compliance Issues,10 CFR Requirements, and Application Documents (cc =' = ")

10 CFR Requirement Application Document (Sectien)

Issue Title (Nunser) 33(d)

Safety Analysis Report Codes and Standards (2.4.3.1, 3.1.3.2.1.1, 3.1.3.2.2.1, (41) 3.2.1.1.1, 3.2.1.3.1.2, 4.1.1.2, 4.1.1.2.3.6, 4.6.1.6, 4.6.2.1.1, 4.6.2.1.2, 4 A.2.3, 5.1.3.2, 5.1.4, 5.2.2.1, 5.2.2.3, 5.2.3, 5.2.3.2, _

5.2.4.2, 5.3.2.2, 5.3.2.3, 5.3.2.10, 5.3.5, 5.4.1, 5.4.1.1, 5.4.1.2, 5.4.3, 6.6.5.1, 6.6.11, 6.6.12, 6.8.1, 8.2,6.10.1.8,6.11.1, Table 6.9,

A

.adix B to SAR 6.11)

Technica Safety R (2.1, 2.2, 2,3 2.5, 2.6. 7) y_11ity Assuranc ogram (2.2.4)

Emergency an (5.5.1.

7.5)

Pac g and Transportation sty Assurance Program (2.2.

h 33(d),76.35(a)(6),

'Satery Wlysis Report (3.9.5)

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UF. Leak Detector 76.123(c) itivity Testing (42) r.chnical Safety Requirements (2.1.3.11, 2.2.3.3, 2.5.3.3)

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10 CFR 21 hnplementing Procedures (43)

(deleted)

N 76.89(a) and (b)

Safety Analysis RLport(3 6.2.2)

Criticality Accident Alann System-Slaved Technical Safety Regmrements Buildings (44)

(2.1.3.1, 2.2.3.2, 2.4.3.1, 2.5.3.1, 2.6.3.4, 2.7.3.2, 2.8.3.1)

U FORTS Rev. 3. 7/9/96 S

h

nix INTRODUCTION On November 7,1995, the United States Enrichment Corporation (USEC or the Corporation) submitted Revision 1 of the Compliance Plan for tbc Portsmouth Gaseous Diffusion Pir.nt (PORTS) to the United States Nuclear Regulatory Commission (NRC). Revision 1 of the Cornpliance Plat.,

which had been approved earlier by the U.S. Departme'n of Energy (DOE), was subtnitted as a part of Revision I to the USEC application for an initial certificate of compliance (hereafter referred to as th Application) in accordance with Section 1701(c) of the Atomic E.lergy Act of 1954 (AEA), as amended, and Part 76, " Certification of Gaseous Diffusion Plants," of Title 10 of the Code of Federal Regulations (10 CFR 76), Section 76.35(b) of 10 CFR requires that the

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Application include the following:

A plan prepared and approved by DOE fcr achievmg comnliance with respect to any areas of noncompliance with NRC's regulaions that are identified by the Corporation as of the date of application that includes:

(1) A descriptio1 of the areas of noncompliance:

C) A plan of actions and schedules for achievmg compliance; and (3) A justification for continued operation with adequate saf;ty and safeguards.

The regulations assign to the Corporation the responsibility for identifying u DOE the noncompliances to be addressed in the plan for achieving compliance. Tb DOE-prepared Compliance Plan includes (1) descriptions of the areas of noncompliance, (2) justifications for continued operation, which describe the provisions to ensure adequate safety and safeguards while the identified r.reas of noncompliance are being elimmated, and (3) plans of act ons and schedules i

for achieving compliance in these areas. Because many parts of 10 CFR 76 and sections of 10 CFR cited therein are performance based, only the NRC can determine whether the commitmems made by USEC are adequate to meet the requirements. DOE has not attempted to evaluate the adequacy of the commitm:nts made in the USEC Application. However, DOE has independently considered whether PORTS per:onnel have implemented the programs and procedures and installed the required equipment to fulfill the commitments stated in the revised Application. Where the current programs, procedures, and eqt.pment differ from the commitments, the nonce.:formances are addressed in this Compliance Plau, whether or not they constitute deviations from applicable NRC regulations.

Revisior.1 of the DOE-approved Compliance Pian addressed those aspects of the operations at PORTS that were identified by USEC in Revision 1 of its Application as not currently being in l

full compliance with either t'.: applicable F"C requirements or the commitments set forth in the USEC Application. Revision 2 of the DOE-approved Compliance Pin, encompassing Revisions l

l 2, 2A, and 2B, addressed (1) those aspects of the operations at PORTS that were identified by l

USEC in Revision 2 of its Application as not currently being in full compliance with either the applicable NRC requirements or the commitments set forth in the USEC Application and (2) commmnents made to modify the Compliane Plan in respcase to NRC questions on the Revision i USEC Application and the Revision 1 DOE Compliance Plan. DOE has prepared and approved this revision to the Compliance Plan to address (1) all PORTS noncompliances identified by USEC in its Revision 3 Application and its responses to NRC questions through July 9,1996, including any new Compliance Plan issv:s not identified in the USEC Revision 3 Application, and (2) all V

commh made to modify the Revision 2 Compliance Plan in the responses to NRC questions regarding Revisions 1 and 2 of the PORTS Compliance Plan.

j PORTS Rev. 3,7/9/96 9

ux s

The existence of the noncompliances described in this plan does not indicate a difference in the overall level of health, safety, and safeguards protection provided to workers and the public under DOE and NRC oversight. Rader, these nonccmpliances reflect (1) areas where compliance has not yet been achieved to existing DOE requirements or (2) differences between the NRC and DOE regulatory approaches to assure adequate protection of the health and safety of workers and the. public and to promote the common defense and security. DOE oversight has generally been from the perspective of a knowledgeable owner-operator, with greater emphasis upon prescriptive requirements and more direct involvement in facility operations. NRC, as an independent reF'.latory agency employing pctformance oriented rules, quite naturally requires more formal 6cumentation and greater formality in operating practices to provide commensurate assurance of adequate safety and safeguards.

In preparing the Compliance Plan, DOE has reviewed the past operating history of the plant as evidenced by assessments, audits, reviews, event reports, and DOE Regulatory Oversight Program inspections. Where past events indicate that USEC is not in full conformance with the programs, procedures, and equipment needed for implementation of the commitments stated in the revised Application, such noncompliances are also addressed in this Compliance Plan. DOE has also determined that the completion of the plans of action and schedules outhned in the Compliance Plan will address te de c ncies identified from past operations.

r Thus, DOE approval of the Compliance P!an is based, in part, upon its conclusion that For the noncompliances identified by the Corporation, the upgrades proposed in the plans of action will, when completed, bring PORTS into compliance with the commitments in the Application.

The justifications for continued operation presented in this Compliance Plan are considered by DOE to be acceptable for assuring adequate safety and safeguards.

p D>

v 3

The plans of actions and schedules for the identifed noncompliances represent an appropriate D-o k[y 3

raeans of bringing PORTS into compliance with the commitments in the revised Application as rapidly as can be safely and effectively managed. Furthermore, the priority afforded e>

individual upgrade actions is, to the maximum extent practicable, commensurate with the

" f S-safety or safeguards risk associated with the noncompliance.

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co 3 2

In several instances, USEC has reported that the plans of actions to elimmate an identified bE #

noncompliance have been completed. 'nius, these issues are no longer USEC-identified y2(Eg noncompliances and the commitments made in their justifications for continued operation are

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j superseded by the implementation of the corresponding Application comnutments. Issues, including

[pi the justifications for continued operation, that have been completed 3 et v:E by ~2E pdct

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te "C :==i ;; r:;;"!::: y =$:dy or by NRC ifar wcsg reg @eg.4eGry, T i" bc E ", f w:.imd in ic Canpiinx "in ud unanted s "s.npkt." A hcr w m p k e n ef i c plim of CP{

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n:isa hn tun =df.:d by L"E cr ".C = :pprepdr, $: i~": ri!! S rh Only in te n

tr.tk of antas li ic =c:!= in ::= 12= 1: m: ": :sd:"

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Subsequent to the Office of Nuclear Material Safety and Safeguards (NMSS) Director's f.

decision on initial certification, USEC will provide quar:erly reports to NRC on the implementation status of Compliance Plan commitments. These quarterly status reports will include, where appropriate, proposed revisions to remove ' '

' w ec %

e that have been i55003 PORTS Rev. 3,7/9/%

o

..___._m

cernpl&d ben ihr.Cc.wpha Mon.

xxxi s'a;cd, The repons will also include an executive summary that identifies plans of actions that

' vere completed during the past quarter, plans of actions scheduled to completed during the next quaner, and a discussion of any plans of actions that are behind schedule. The execuuve summary will b-supported by a detailed listing, soned by noncompliance, of the individual commitments within each plan of action. The listing will include a comparisen of the comnutment completion date with the current projected completion date for each individual commitment that has not been completed. He first such report will be provided to NRC no later than 90 days after the NMSS Director's decision on inital certification. Rese repons will provided until either all plans of action in the PORTS Compliance Plan have been completed or the NRC agrees that the reports are no longer necessary.

In addiion to the commitments made in the Application, USEC has made commitments, relating to nuc%ar saferv and safeguards, to DOE under the DOE regulatory oversight pro;; ram.

To ensure that no USEC commitmems to safe operation are lost in the transition of regulatory oversight from DOE to NRC, DOE will provide to NRC: (1) a listing of all open regulatory oversight inspection items affecting PORTS, including references to supporting inspection reports or correspondence, (2) copies of draft PORTS regulatory oversight inspection repons awaiting issuance on the regulatory oversight transition date, (3) summa, u of the findings and concerns identified during any inspections for which draft in mection reports had no. been written as of the regulatory transition date, and (4) a listing of all open USEC commitme cs affecting PORTS that were made in response to regdatory oversight inspections, modifications to the Regulatory Oversight Agreement, or other regulatory oversight activities, including references to supporting inspection reports or correspondence. These listings of open regulatory oversight issues and commitments, the draft regulatory oversight inspection repons, and the inspection fmdings summaries will be provided to NRC by DOE within the week after NRC assumer responsibility for regulatory oversight of PORTS.

' Ibis Compliance Plan roughly parallels the structure of the Application with the compliance issues presented in approximately the same order as the most significant of the commitments addressed by each issue. The Applica: ion describes aspects of the operations at PORTS as they will be when PORTS is in full compliance. In those cases where some aspect of the operation is not currently in full compliance with applicable NRC regulations, the noncompliance is described in the Anolication and in this Compliance Plan, as required by 10 CFR 76.35(b)(1). Ir. the interest of simplicity and clarity, several of Me individual Compliance Plan issues address multiple specific not. compliances identified in the Application. As an aid to the reviewers, the linkages between the Compliance Plan issues and the noncompliances cited in the Application are shown in a table at the front of this document. To aid la locating the compliance issues, this document also includes a table relating each comphance issue to the corresponding NRC regulations and to the sections of the Application that contain the commitments referenced in the compliance issue.

In some of the compliance issuea, the phnned actions described include operational enhancements that are not, in the judgment of DOE, necessary to meet the applicable NRC requirements. Such operational enhancements are not the fmancial responsibility of DOE tmder the Lease Agreement between DOE and USEC. These operational enhancements, which generally are related to activities required to actueve compliance with the NRC requirements, are discussed in this plan solely to provide a more complete description of the proposed upgrades. The complimce issues for which the planned actions include this type of operational enhancements are identified in the Contents by an asterisk at the end of the issue title.

PORTS Rev. 3,7/9/96 s.

'O

uxii in compliance with 10 CFR 76.33(e), those portions of the Compliance Plan that contain withholdable information have been placed in the Appendix. Withholdable information includes Restricted Datz, National Security Information, Safeguards Information, Unclassified Controlled Nuclear Information, proprietary data, and other such information. Where withholdable information is required to describe a noncompliance, jusufy continued operat'on, or present p'anned actions and schedules that would otherwise be in the body of the Compliance Plan, the compliance issue is diesW in the Appendtx.

The Compliance Plan discussion begins by referencing the regu!atory requirement and restatmg or summanzing the incompletely met commitment from the Application. The dis:ussion continues with the following:

description of the specific area (s) of noncompliance [per 10 CFR 76.35(bXI)],

justification for continued operation with adequate ufety and safeguards (per 10 GR 76.35(b)(3)], and planned actions and schedules for achieving compliance (per 10 CFR 76.35(b)(2)].

This discussion is followed with a table that links the Compliance Plan issue 'vith (1) the applicable regulatory requirements, (2) the relevant commitnent stat ments from the App!ication, and (3) the noncompliance statements listed in the Application that are addressed by the Compliance Plan issue.

In summary, the Compliance Plan contams the information required by 10 CFR 76.35(b) and has been prepared and approved by DOE, as indicated by the signatures on the approvals page.

PORTS Rev. 3,7/9/96 e}

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