ML20237F143
| ML20237F143 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/15/1993 |
| From: | Long R GENERAL PUBLIC UTILITIES CORP. |
| To: | Masnik M Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20237F129 | List: |
| References | |
| FOIA-98-175 C312-92-2089-7, NUDOCS 9809020087 | |
| Download: ML20237F143 (14) | |
Text
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GPU Nuclear Corporation M.ccletown. Pennsylvania 17057 0191 i
TELEX 84 2386 I
Writer's oirect Dial Numoer (717) 948-8400 i
January 15,1993 CU3W 92359T 0000-92 1968 l
Dr f,1 i f.d e,ru I'DNP D rt'n' orate US Nu';' ear Regu.atory Commise..nn
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..... :..,:. DC :'OCCC SUBJECT. Proposed list of PDMS Rcqu:rements and Commitments Ocar Dr. Masnik.
On December 8,1992. a public meeting was he!d at the TMI Training Center to discuss the proposed hst of PDMS requirements / commitments that were forwarded by your December 7,199? letter.
As discussed at that meeting, we understand and agree with your
- Requ.rements for issuatice of the POL."" Requirements for issuance of the PDMS Technical Specacatioris." and the beense conditions contained in the " Acquirements for Entry into PUMb truM5 tecnnica: specifications occome ettective)." Enclosure 1 pre:ents the GPU Nuclear position / status on cach of the abovo referenced items. There were changes, by l
mutual agreement during the December 8th meeting, regarding the " additional requirements or licensee commitments [thatj must be met prior to entry into PDMS." Enclosure 2 provides our under-*anding of these roca.rements wit') ch,nges indicated by a vertical hoc in the magn P ease re. ew the attgr:ec inintmation and advise us of your acceptance. We understand tv turna: trans.nttai c' tras lint will :$ccompany the TMI.2 Possession Only License.
Sincerely.
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.u, l<+oi allow the implementation of PDMS is not expected to be issued until just prior to entry into PDMS and after the :taff verifies that all the requirements and commitments that we have agreed upon have been met.
I request that you review the proposed list of PDMS requirements and commitments contained in the attached January 15 1993 letter from GPUN and let ma knnw by tha middle of April 1993 as to its acceptability.
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N Seymour 11. Weiss, Director Non-Power Reactors and Decommissioning Pro.iect Directorate Division of Operating Reactor Support Office of Nuclear Reactor Regulation rt w/ enclosure:
JRoqqo, Rl Mivans, R1 iYoung. RI UlS!FlWiloN:[Bloucli. }[Masnik diskette-lbl Docket Iile fHylton ONDD R/F MMasnik BG r i me's Clieh l. R l SWeiss ONDD tA ONDD:PM /
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.t them ac:essible at the Thil 2 site.
He staff wdl senfy by reviewtng the pnmary l
documentation and or tntpection of the actual modification. Once the staff has conducted m resitw and determmed that the requirement or cormmtment has been satisfied. the staff will close out tbc item. As other items are completed, the licensee will contmue to notify the staff in wnting of the completed status and idenufy the appropriate pnm references. The staff and beentec plan to acree pnor to notificadon of completion of an tictu w hat constitutes the standard for demonttmung compledon of the item.
ht PE!)G.f2tJEFJ f.0.E _ f.11ANOB'O Tim Anovn RtiQUIRENENTS _,,,LW QMMITMik"[S l
l During the rrmainder of the curn:nt cicanup effort, conditions may change resuldng in k
1 a enange m tne acensee s sotnty to sausiy tne above nquirements and commitments.
l Licensee's request for desiations to the above hst of requirements and conditions muy be made in w nting, as an amendment to the SAR. providing a description of the old requirement or commitment and a descripuen of the change The deviation requeet must melude a safety analysis naluaung the proposed change Reque.its for deviadons to the n'< u: he must b" tuort) and allow fi r staff rvs new (ty}ncally 60 days). He NRC staff w di tither approve or disapprove inc licensec's rrquest in writirig based on the results of the staff review ne licensee understands that PDMS was evaluated and received st.tff a;yruval ba>cd en the requittments and mmmittnents made by the brensec through S \\P Amendment 15 Lenificant changes to the requirements and comnutments may in..ihdatt or risport a rrci aluatmn of the staff % Safety Evalualmn and Tahmcal inatuation kegon I
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L liwM2Mecten 1.
Ensure that Hood panels art pmvided for all entrances to the control building, and to the entrance of the auuliary building. (TER 6 36) Doors and entrances to the Control Budding Arca that are not Good-protected are cither watertight or are provuled with Good pancis. All operungs that are potential leak paths (i.e. ducts.
j pipes, conduits. table uap) arc scaled. (SAR 7.1.4)
Verify that the containment basement and auxiliary building sumps level indications will be mamtained. (SAR 7.2.3.1.2) l N fy thst thr* auuliary bmldinc sump putnps art snairitained o}n stional and placcal m a manual control mode (S AR 7.2.3.1.2) 4.
Venfy that the hiiscellaneous Waste Holdup Tank and the Aux.iliary Building Sump Tank (ABST) have been isolated from the Radwaste Disposal Gas System and vented via HEPA filters to protect against airborne releases from these tanks.
(S AR 7.2.3.1.2) 5.
Ensure that a Cow path exists to drain down the reactor building basement floor.
(SAR 7.2.3.1.2) o Veril. dai fauc pictccion ha:: been provided for portions of the Waste Disposal Liquid (WDL) system that art detennined to be subject to freezing due to deactivation of building ventilation systems. (SAR 7.2.3.1.2) 7.
Verify that attemate provisions have been provided for operating the air-operated valwt ruluirn! for the WDI. system during PDh1S. (SAR 7.2.3.1.2) 8.
Ensure that the active sumps have a high level alann that annunciated in the control roorn and the PDh15 Alann hionitoring System (SAR 7.2.3.2.2)
K.
Ifr.ccedor.cs_ arid Prps.rarns 1.
Include a surveillance program under which a litnited number of rixlent carcasws will tx: analyzed for gamina-crnitting isotopes as part of the non routine Radiological Environmental htortitoring Progmtn. (SAR Supplement 3. A-16)
L S T A N D A 8 DS TMU.. S.o T)S ID'UiG_ REG.!1BQ1Eb7.SE!D_C.OAih_ilTALEb'T.S.
The ctatf recognizes that inany of the above rtquittments and commitments have been acted upon by the licent.cc Once this list is finalital, the 1.icensee wilj submit a letter that documents which of the listed requirements and commitments have been satisfied TL h:nct w ill reference primary documentation (UWis, proceduit numbers drawinp.
ric i that demenstr.ite that the worh was comp!cte41 or the nx{uirernent or commitment I
mei 11 v.dl not be necessasy to submit the piimary referenec documents but only base m________---_-_--.
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[p, sw;4ais p.3; 12.
Ensure that the fire system line is cut and blanked off at the fuel handling l
budding, where the fire system line runs from the diesel generator building (SAR 7 2 2 2k TER 6-32) 13.
Deactivate the in er water purnp house. (SAR 6.1.10 and Supp.1. Item 14. TER l
6-33) 14.
Turn over the fire purnp house and fire pump 2/FS-P 1 to Unit 1. (SAR 6.1.10 and Supp.1. licm 14. TER 6 33) 15 Ensure that transient combustibles have been removed from inside the l
contautment and the AFHB to the cuent practicable. (SAR 7.2.2.2g.: TER 6-33)
Ttus mcludes most plant ecms installott after the accident. Fire loading m'ist be less than a 1-hour loadme of 80.000 BTlusquart foot. (SAR Supp.1. Item 17) 16.
Dram oil to the extent reasonably actucvable from the main turbine main l
feedw ater pumps. emcreeney fecdwater pumps. steam generator feedwater pumps.
condca. ate booster pump reservoirs and hydrogen seal ou unit. (SAR 7.2 2.2h..
TER 6 34)
I 17 Talen as an aggregate. demonstrate that no more than 57 percent of the original total solume of reactor coolant pump lubricating oil remains in the upper and I
inwer rncrvmr,. of the four rextor coolant pump reservoirs (S/W Supp.1. Item
- 33. TER 6-34)
IS Charcoal filters base been removod from a!! IIVAC systerns in Thfl 2. (SAR l
7.2.2 2s. TER 6 34) 19 Train and famiharue station tire bngade with the TMI 2 system configurations.
l plant layout and procedures for TMI 2. (SAR 7.2.2.2m. TER 6 35) 20 Pmcedure in place for reactivation of the deactivated portions of the fire l
protection system if necessary. (SAR 7.2.2.21.; TER 6 29) 21.
Verify that the procedure for inspection of the fire loop drain valves during frtczing weather is in place. (SAR 7.2.2.2k.; TER 6-32) 22.
Verify that the procedures and system are in place for testing of the operab!c l
portion of the fire detection and alarm system. (SAR 7.2.2.2b.: TER 6-34) 23.
Verify that pmcedures for rnanual suppression of ftre by the fire brigade are l
provided as stated in the FPPE. (TER 6 35) l l
L___._-_____________-__--
t 1.
Fire Protoc.ti.e.0 line pn<edaru in plate to ensurr that the fire mains within the tractor buddmp u dl be closed with sajvn drained to the extent trasonably achievabic within 30 days follow ing entry into PDMS to mirumize the potential for introductwn of water into the reactor sessel. (SAR 7 2.2.2.2k.. TER 6 2)
Ensure that automatic fire suppression a provided and maintained to arcas of the l
facibty and <ystems wtuch cent.ua significant amounts of combustibles and p>ssib!c ignition sources (i c. auxiliary transformers). (SAR 7.2.2.1) i
.i.
Ensure that either the TMI 2 contrul room or some other location is coridnuously manned with a fully qualified permn or that remote mordtor ng capabilities are as atlable m TMI 1 wntrol room to identify the speedic zone m wiuch a fire in the TM17 tarihty n located Ensure that procedural control custs to dehneate the lomatien of the monitormg activity ITER 6-29. SAR 7.2 2.2b.)
Demonstrate that TMI l Operations has accepted responsibility for maintaining l
4 the fire service system in operabic areas of the plant as rtx{uired to suppon operations. in the waste handling and packaging facibty, the respirator cleaning facility and the administration buildtng. (TER 6-29)
Deactivate deluge systems in the aunliary building and the control building. (SAR 7.2.2.3. TIIR 6-29) 6.
Ensure that all lialon systems have been deactivated by disconnecting the l
cylinders and either emptying or removing them. (SAR 7.2.2.2d) 7 Verify that ponable fire extinguishers are located.n o, areas speciDed in Figures l
7 2 6 and 7.2 7 of the SAR (SAR 7.2.2.2e.)
I 8.
Verify that self contained breathing apparatus art available for fire fighting j
purposes in the areas shown on Figures 7.2 6 and 7.2 7 of the SAR. (SAR 7 2.2.2f.)
4 Fnturr that the fire detection system rtrnains operationalin the Air Inta.ke Tunnel l
and the relay nom. (S AR 7.2.2.2d.)
10 Ensure that frecec protection has been added to applicable portions of the fir l
main (S AR 12 2 2j ; TER 6 31) 11 To the nient that fire prot <voon is not requirrd in werk or storage areas. ensure imbtirn of the !? meh fitt service 1 = 9. w hu h runs through the AFIIPs the l
, entrol building arca and the turbmc hmidmr (eaM and w esti (SAR 7 2 2 2k T ER 0.O fgiw Z n %
11 l Agqu al Related i t.
n a. to w m.o.. m e n t. rex tor knldmg electric power circuits w ill be decncrytred escept th0tc necessary for PDMS morutoring. tospection and surveillan/c egiipment and other PDMS suppert requirements (SAR 71 14 Supp 1 liem 17 TliR 6 34 and 6 3S)
In the.muhan f unkhn;- the gewer to lightmg. fire drietters. and sump lesel mdhatun ( m u:Is a tu tv ( nert:ticd and wdJ remam eperationa.l.
The auutary somp. anuhar,. sump tartk and associated lesci indication will also remaan operational. (SAR 7.1.2.1 TER 6-37)
]
3 In the fuel handling building. Iow voltage circuits to lighting and ftre detection l
will be energued. (SAR 7.1.3.2: ~1T.R 6-37)
In the Control and Service Buildings, verify that the electrical distribution will 4
remain configured to power Inw voltage lighting loads and ftre dctcctors. (SAR 7.1.7.2) 5 Ponions of the TMI.2 electrical di.stribution system wiJl be operational and l
cnergized to proside power for the PDMS sugwrt systems and their associated controls and instunnentation.
Power will be availabic for arta lighting.
receptacles, heating and ventilation to suppen PDMS activities. (SAR 7.2.5.1.1; TliR 6 37) 6.
Emergency lighting (S hr penabic cmcrgency lights) is staged with ernergency rrspome ( trw eqmpment (S AR 7.7 53 1. TER 6 3 7)
Venf> th.it cut signs are powered from the normal lighting 53 stem and frorr a locally mounted battery during emergency conditions (SAR 7.2.5.2.5) 8.
DC power during PDMS will be available. loads have been consolidated where practuaHe to c do.r the number ef encrp.:cd urcuitt (SAR 7 2 513. TiiR 6-3Si 4
Venf n thir dire (r current had.up (< u ct supphes are provided to the (upport r.nhano.. momtoont danne a tempor:n> Ims of pow er (SAR 7 2 5 1 3.11R 6-15s i
2 Updatt mfunnauon in the follow tog tables from the SAR as final decontaminauen resula tamne asailab!c. (SAR 5 4.3) i Table 5.3-2 (SAR) "PDMS Rad 2clogical Conditions - AFHB
Table 5.3-4 "Surfacc Contaminadon - Reactor Building"
- Table 5.3 5 " Surface Contamination - AFHB" Table 5.3-6 " Surface Contamination - Otber Buildings" 3.
P :f:rm :..':y Of th: ::..S:: bt!! ding, elevation 305 ft.; the turbe building, elevation 281 ft, and the containment air control envelope building and provid infonnation in the PDMS SAR before entry into PDMS in order to establish a radiological baseline for the facility. (SAR 5.3.2; TER 4 2) 4 Ensure that a program exists for penodic measurement of radiacon and cont;umnacon levels to ve dy radiological conditions. (SAR 7.2.4.1 and 7 2.4 2.
TER 6-12 and 6-43).
E.
Php,r.c.al), maintenance in Reacter HuiJdine and Vessd 1.
Ilave the capat,dity of inseninc a video camera into the reactor vessel to venfy fuel location if it is detenmned at a later time that such an examinaaon is required (TER 6 3)
Citate a pnyr.un plan to perfonn rnenthly entries mto the.eactor building' for at
..TER F
Ilhnei.al ? Iamtuurto: in AFilB l
Crr.vr. pnigram pltn to perfonn montiily entries into the AFIG for at least 6 rnonths dier p! acing it into its PDMS condinon. (SAR 7.2.4: TER 5 23) i 2
Ensure that both fuel pool structures rernain intact (SAR 71.3.2)
G Ptn.,0.' 3f amien,ms t in ghet St.ijdings
!%u rc that ibe ('ontrol Room Venalation Splems O c.. Centrol Room IIV AC and Cable Nirn HV AC) and the Serv ce Building Ventilauen System alt mamuinal in an operational cond2tico and will be operated as required. (SAR 7 7.6.8.v.10) 2-Maint.un the capabdity to process potentially contaminated liquids.
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c to 15 s ve nu r.w C.
Ec.rtt,i,latip.n i
Verify that a survedlance progntm exists to ensure AFHB ventilation and
~
futration operabiUty, maintenance and testing. (SAR 7.1.2 and 7.1.3; 'ER 6-26) 2.
Verify that the licensec has procedun:s in place to continue to operate the AFHB venttlatwn system until the Accident Generated Water is no longer being processed or transtccred in the AFIIB. (TER 6 28) 1 Ensure that penetration R 626 has been upgraded to 5 psi. (SAR Supp. 3, Item l
]
B.2; TER 617)
Ensure that the rtuctor building breather system is the predominant pathway for N
4 cffluent and mGuent to the building during those times that the ructor budding ventilation system is not being operated; and that the efGuent is GJtered and monitored IS AR 7 2.1 ?. TER 6 25).
s DOp tett the llEPA fHrer in breather pnor to entry into PDMS (SAR 721.2.2 l
5 and Supp 3 Item B-). TER 6-25)
Ensure installatmn. ai.tuatwn serttng, and roudne surveillance testing of the 6
isol.inon sabe between contamment and HEPA fUtcr in the reactor building ottam r no automatsc.tay close ujun rneipt of a contamment pressure mercase r
of U 25 pm (S AR 71 1 2: TER 5 10. 5 1 J. and 6 24)
Devclop and implernent a tractor building entry procedurt that requires an evalualmn of the re ictor building atmospheric conditions prior to personnel entry tV 4 D 7 9 f 1) 7 E
Ibelop and,nop!cmen: pris edures for trwnfainim' HEPA Glier banks for the Rem for P.utiding INrge Sy stem.(S AR 7 / !.31 O
Desclop and implernent pn)cedures for rnonitoring the Reactor Building vent durmg tractor htniding purlie (SAR 7 2.1.3) i i
D P.lVit.C.qr).tAtnma11ca S,u,rEv l
l 1.
Licensce wiu meet established contaminadon level goals for entrance into PDMS i
for each arra of the AFHB. If the slecontaminaden goals cannot be rnet because of the umque situation at TMI.2 or ALARA considerations, the Ucensoc will pn> vide an evaluation of the specine situation to the NRC. (SAR 5.3.1 and Supp.
- 3. Itern A. ll; TER p. 4-2)
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ENCLOSURE 2
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Addjtionajlequirrmr.DL5/Licensec Commjttpenu A
Remeva.l of WELet from Reap 1,qr _Cpp.lanLS s. tem anMuel,,'[rMs{er Canid i
1.
Remove water to the extcot reasonably xhiesable.
Reactor Vessel; drained to less than 10 gallons (38 liters) of water TSAR 6.2.27.2: TER $-9; Reactor Building l'uct Transfer Canal (TER 5-9) 2.
Isolate the fuel tmnsfer tubes. (SAR 1.1.2 !).
3.
Dnll holes in canal seal plate to prevent refuelinc canal from filling ITER $ 9) 4 Cover the Reactor Vessel to minimize water entn. (SAR 6.2.27 2)
Drain the Submerged Demmeralizer 5,utern to the cuent scawnably actuesabic.
iSAR 6 2 36 2; 6.
Drain and shield the "B" spem fuel pool to the extent reasonably achiesabic.
(SAR 6.2.36.2) 7.
Drain and cover the "A" spent fuel pool to the extent reasonably achievable.
(SAR Supp. 4. Item 1)
E.
Ba.d.i.a.tiqn_S.af.c.ty_4: B.edy.cintLalPRtsstia)_for PeIent.!
1.
Ship offsite or package and stage for shipment remaining rad!oactive waste from the major ThD 2 decontamination activities. (SAR 1.1.2.1: TER xiv) 2.
Reduce radiation levels within the facility, to the extent reasonably :chievable and consistent with ALARA, to allow plant rnonitoring, maintenance. t.nd inspection-.
Apply shiciding in criticallocations after rc.ictor vessel draindou n to reduce desc ratet (TliR 5 23) l 1
Define and establish an overall surveillance program plan for PP'!S cnsininmental protection systems to ensure pnblic hcalth and safety. (TER xiv)
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=
tt>s -rc. lor 3:ig rKs t fill L f cElr$l16 TO IG. I A9 816 F. (X d.
Post Dcfueling Monitored Storage Fire Protection Program Evaluauon il PW) The staff will.eview this document. which the licensee will hkcly tubmit.tust before entering PDMS.
l 9P_UJ.ue. lear Statur The FPPE will be trvised and submitted just prior to entry into PDMS.
Radiological Environmental Monitoring Plan (REMP) Requin:s NRC r
review iust tyfore the stan of PDMS. Currently the licensee has a TM1 utt RiiMP with re4tundant requirements m the TMI 2 Appendi.x B techtneal s;wctfications The staff will review the site REMP approumatels 2 months befort entenny PDMS to venfy that the programs discussed m the PDMS SER are included. The radiological enstrotunental monitoring trquirements in the current Mode 3 TM12 Appendit B techttical specifications art to be deleted by a Ucense amendment to be issued independently of PDMS and prior to entry into PDMS. These requirements wi!! be placed in the Offsite Dose Calculation Manual.
GPU Ntteley_ $.tAry2: GPU Nuclear submitted this plan via GPU Nuclear letter C312 92 2091. dated January 4,1993. There should be no further changes necessary to it prior to entry into PDMS.
f.
A revision to the PDMS SAR, to include the results of the completed plant radiation and contamination surveys just before entering PDMS.
.GRU, Nuclear Stattm The SAR wiu be revised to include this information and subrnitted nrior to entry into PDMS.
l wwww e-__-_-_-__------_--------.
t a + - j a :.; 11 ;o rxet 11 1 L l'Etr'Itr.
Tu t'.
- male VF (jptf Nugby St;itu.s GPU Nuclear has courcted Iw o quarters of data m the 1:nci lian.thne Buddmg and four quarters of data m the Auuliari Building Th u er'.i saw p;irti. daic rthme rate frorn the m quancr:, of data is less than 2'i of the hcense condition crit < ria We should have no problem collNting the requisite 1 year of pre-PDh1S data.
B 1 wense ('onihtion ? E *17nfHrcred leak Rate Test. " The Ucensee needs to develop (and submitJ a[n appruvnlJ surwillance requirernent for the reactor buijdmg unfutcred leak rate test (Section 4.1.1.2) to demonstrate compliance with 1.imiting Condition for PDh1S 3.1.1.2.
.G.P_tLN.u. cleat $nitur A proposed unfijterrd leak rate test surveillance requirement woi oc suomitted witn PDh1S SAR Amendment 16. which will be submitted by January 22.1993.
C.
License Condition 2. F. " Additional Submittals Prior to Post Defueling hionitored Storarc."
According to the proposed POL the foUowing docurnent* need to be submitted and in wmc cases approved before the facility can enter PDh15.
Site Fbod Protection Plan Requurt NRC res e:w The hcensee plans a
to tubmit the p'an b.s the end of 1092 GPt '.yoi. lear Statu>
GPtf Nuclear sobrnittui this plan sia GPU Nuc! car letter C312 92 2001. dated January 4.1993 b
So'r Palanon Prctecnori Phn Hrqunes NRC res ww The hecnwc pbn' t *.obmn the plan by the end of IW2 U.Ptl Fut. car _.Statu.(
GPU Nuclear (uhinitted thic, plan via GPI,'
1 N,j. lc.o letter ( 11 ?.O.?.N01 dated Janu.ory 4.1003
( >llute !)otr ('ak ubrion Marnial (( >DCM Fequires NRP res icu and c
appt.w al and a In i rnt.unernhntnt to INI ? htenw On June 18.
t w? the staff o, rim! an acceptable UDUM from the hcensee The (tatt o pnw.emnr a hii nw amenihnent for TM12 w hich should I -
. cmpleted b,s the end of 1002 The staff should apin review the t )DCM tutt before ihr h< cnux cnters PDMS to serify th:it reference <,
in the-UDCM to the Mr=1c 3 technical ynifk.itions base twn trrnos..I and th1! enforruatuen rrgarthng the reactor bothhne breather h t', f r. s'ri in60i[w erated t.Pt ' '; ic h at 'q no.s the t II)CM w ill tw n:s o.r d an.1 subminoit io i
[ r n ' tr. t on s noe Pl >MS d
Post.Defochnr Monifered 9 orace Farr Prote. tion Pn7 tam Fvdoanon t
7
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IU 14. 1645J118 F'. U.J I
2.
Development of a procedure for NRC staff authornation to enter PDhtS.
The staff proposes that the PDMS Technical Spccificadons be issued at the time the POL is issued. The PDMS Tecimical Specifications would be in effect only afict
')
NRC staff authorizadon.
De staff authoruadon would be granted once the licensec cenifies that all requirements and commitments for PDMS (see W.
below) have becn satisfied.
i GPU Nuqbar_P_ojitjes: GPU Nuclear agrees with the staff proposa].
3.
Development of a PDMS punchlist that lists requirements and commitments that aere pan of the PDMS SliR and TER review. This list was inidally developed by the NRC staff.
l GP.Il Nuclear._lio,s.i,t;,gn: Tlus letter and staff acceptance of same errates the subject PDMS punchlist.
Development and licensec agreement of a standard of what constitutes completion a
And What is reQulted for NRC verification of open items. During the open meetint to dncuss each of the stems in m below the staff and licensee wdj agree upon w hat funn of pnmar) documentation is requned for each item This issuc is f urther do. cussed in item W L below
'7 P U_ ". '. -. "v :... OPU '.'u.!= a;:rees w ith the staff proposal in item III L 5
i Develo;> ment of a prr>cedure for resohinc deviations from the Dil-2 punct list Once the bst of remammg actiuties has been agreed upon by both the bcensee l
and the NRC then turun: chances to the list wdj have to be documented. a safety
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evalualmo tierfonned bv the hcensee. and NRC staff review and approsal of the dm.o.o.inerhynyc Tins niere t! 6.ussed further in item m M below I
QPANurirstilentjen: GPli Nuclear arrecs with the staff proposal in item I
i W.M 111-RI.()I lH IGIENTS l'O R ENTRY INTO PI)MS (PmtS TECIINICAL SPF( li'ICATIONS lil CONTE EFTI.CTIVIO
)
I The following an; the conditions in the Pmposed PDMS POL. contained in the Febniary 70. 1902 lener, that must be met pnnr to the entry into PDMS:
A.
Liecnse Condition 2. D. "Special Auxiliary and Fuel liandling Building l
Ventihtion Snidy." The monitoring pmcram (that is required prior to terminating continuous operadon of the AlHB ventilation systems] shall include at least 1 year of data before entry into PDMS. The bcensee currently has collected two quarters of pre-PDMS data.
L
A ENCLOSURE 1 i
1 Requ_i eJuants for issuanc.c.pllhc_EOL.an_d_ EDA 1S_T.cc.hnical Soccificaticos.,
t ar'(! IheJPNS. Liceme Condi.tj,oJn i
REQUIRDIENTS l'OR ISSUA.NCE OF TILE POL 1.
Befort the staff can issue the POL the Ucensec must submit the final Po Defueling Sursey Report [PDSR) for the Reactor Vessel [RV) that provides both an estimate of the quantity of remaining fuel and demonstrates that the fuel will rem.un tuberitical. The staff w ill review the Ucensec's submittal and conduct an mdependent assessment of the criticahty potential for both the srcady state and accident %cnanos EPU Nuclear Startn: The RV cnticality safety analyses wcre submitted via GPU Nuclear letter C312-97-2080. dated December IS.1992. The RV PDSR wi submnted by Pcbruar,,1.1993 Ley.ue being submitted separately to facditate I
NRC resiew
?
ne statement, in paragraph 2. A of the proposed POL. '
and is desenbcd in the Pest Defueling blomtored Storare Safety Analysis Report as supplemented and amended and ihr Fnviinmn, m..I th port as supplemented and amended" needs to be revacd.
The identified documents describe the facility as it would be conficured durme PDMS and not the cuntnt Mode 3 conditaon.
QPl
- Nu,1 car S. tan _g A proposed reunen to this statement wdl bc submitted by January 22.1993 along with PDMS SAR Amendment 16.
3 Pargraph 2.C (1) of the POL refers to the Technical Specifications contained in Appendix A only. This refers to the Technical Specifications that would be in force after the licensec enters PDMS. The current Technical Specifications stt'il l
have a part A and part B. Ec proposed PDMS technical specifications has only an Appendix A. Dettfon: the POL would have to be changed to reference toth A and B.
C9J.Uioc,1, ear _S_tAtg A proposed revision to this portion of the POL will be l
submitted by January 22, 1993, along with PDMS SAR Amendment 16.
ff.
REQLTRDfENTS FOR ISSUANCE OF
'IllE PDMS TECHNICAL l
SPF.CIFICATIONS I
1.
Resolution of the amount of fuel rvinaining in the tractor ves. ten and the potential for recriticality.
i Q P( N't.).tr [I.itus $4mc as item I I alVs c