ML993410218
| ML993410218 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 11/19/1999 |
| From: | Colburn T NRC/NRR/DLPM/LPD1 |
| To: | |
| References | |
| -nr, -RFPFR | |
| Download: ML993410218 (17) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION "WASHINGTON, D.C. 20555-0001 November 19, 1999 LICENSEE: GPU Nuclear, Inc.
FACILITY: Three Mile Island Nuclear Station, Unit 1 (TMI-1)
SUBJECT:
SUMMARY
OF OCTOBER 27,1999, MEETING WITH GPU NUCLEAR, INC.
REGARDING LICENSING ISSUES AT TMI-1 On October 27, 1999, a public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and GPU Nuclear, Inc. (GPUN or the licensee), at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, MD. The purpose of the meeting was to discuss the status and completion schedule of active, and soon to be submitted, TMI-1 licensing issues. Also briefly discussed was a proposed licensing workshop to be held during the first half of year 2000. Attachment 1 is a list of attendees. Attachment 2 is a copy of the licensee's handout used at the meeting.
Major changes since the previous meeting on August 13, 1999:
Completed NRC Staff Action:
The staff closed TAC No. MA6284 which was opened following receipt of the licensee's August 16, 1999, letter, requesting NRC staff approval of the licensee's analytical approach to resolving problems with the TMI-1 pressurizer support bolts. The licensee subsequntly issued Licensee Event Report (LER) 99-006-01 documenting that it had completed modifications during the 13R refueling outage to address the issue. On this basis the staff considers the item complete.
The staff issued License Amendment No. 214 on August 19, 1999, approving revised core safety limits to allow up to an average of 20 percent of the steam generator tubes to be plugged. This completed the staff's review under TAC No. MA4301. This was an item upon which the approval was a contingency of the sale and license transfer of TMI-1 to AmerGen.
The staff issued License Amendment No. 215 on August 24, 1999, and an errata to the Safety Evaluation on October 14, 1999, to allow a one-cycle approval for increased technical specification leakage of engineered safeguards feature systems outside containment. This completed the staff's review under TAC Nos. MA0246 and MA4665 for Three Mile Island Unit 1.
The staff issued License Amendment No. 216 to add technical specification requirements for the TMI-1 remote shutdown system on September 22, 1999. This completed our review under TAC No. MA3950.
Other changes:
The licensee identified several technical specification change requests which it has not yet submitted and reviewed its submittal schedules and the date the submittal reviews would need to be completed. The licensee identified several changes to the dates provided in their handout. Specifically, the requested approval date for the Inservice Inspection (ISI) relief NRP_ 0CVt<
request to be submitted by November 30, 1999, was changed from June 2000 to September 2000, as was the approval date for containment ISI inspection reliefs expected to be submitted by November 15, 1999. The submittal date for License Change Request 290 was also modified from March 1, 1999, to September 1, 2000.
Timothy G. Colburn, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management OffiCe of Nuclear Reactor Regulation Docket No. 50-289 Attachments: 1. List of attendees
- 2. GPUN Handout - GPUN/NRC licensing activities list cc w/atts: See next page
November 19, 1999
-2 request to be submitted by November 30, 1999, was changed from June 2000 to September 2000, as was the approval date for containment ISI inspection reliefs expected to be submitted by November 15, 1999. The submittal date for License Change Request 290 was also modified from March 1, 1999, to September 1, 2000.
Original signed by:
Timothy G. Colburn, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289 Attachments: 1. List of attendees
- 2. GPUN Handout - GPUN/NRC licensing activities list cc w/atts: See Next Page Distribution:
HARD COPY E-MAIL File Center PEselgroth, RI (PWE)
PUBLIC SPeterson (SRP)
OGC MO'Brien (MOB)
PDI-1 Rdg. EAdensam (EGA1)
ACRS JZwolinski/SBlack (JAZ/SCB)
TColburn (TGC) MTschiltz (MDT)
DOCUMENT NAME: G:\PDI-1\TMI-1\1027MTS.WPD To receive a copy of this document, indicate in the box: "C"= Copy without attachment/enclosure "E" =
Copy with attachment/enclosure "N" = No copy OFFICE NAME PDI-1/PM TColburn/rsl t POT-L MO'Brien - H PDI-1s SPeterson H
DATE //99 / 99 i / 99
\OFFICIAL RECORD COPY
November 19, 1999
-2 request to be submitted by November 30, 1999, was changed from June 2000 to September 2000, as was the approval date for containment ISI inspection reliefs expected to be submitted by November 15, 1999. The submittal date for License Change Request 290 was also modified from March 1, 1999, to September 1, 2000.
Original signed by:
Timothy G. Colburn, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289 Attachments: 1. List of attendees
- 2. GPUN Handout - GPUN/NRC licensing activities list cc w/atts: See Next Page Distribution:
HARD COPY E-MAIL File Center PEselgroth, RI (PWE)
PUBLIC SPeterson (SRP)
OGC MO'Brien (MOB)
PDI-1 Rdg. EAdensam (EGA1)
ACRS JZwolinski/SBIack (JAZ/SCB)
TColburn (TGC) MTschiltz (MDT)
DOCUMENT NAME: G:\PDI-1\TMI-1\1027MTS.WPD To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" =
Copy with attachment/enclosure "N"= No copy OFFICE PDI-I/PM PDI-1/LAii : ,'
ýI PDI-I/Sýp,,-*
NAME TColburn/rsl MO'Brienf'" SPeterson DATE ////(/99 / ' /99 it /\%/99 OFFICIAL RECORD COPY
Three Mile Island Nuclear Station, Unit No. 1 cc:
Michael Ross David J. Allard, Director Director, O&M, TMI Bureau of Radiation Protection GPU Nuclear, Inc. Pennsylvania Department of P.O. Box 480 Environmental Resources Middletown, PA 17057 P.O. Box 2063 Harrisburg, PA 17120 John C. Fornicola Director, Planning and Dr. Judith Johnsrud Regulatory Affairs National Energy Committee GPU Nuclear, Inc. Sierra Club 100 Interpace Parkway 433 Orlando Avenue Parsippany, NJ 07054 State College, PA 16803 Edwin C. Fuhrer Peter W. Eselgroth, Region I Manager, TMI Regulatory Affairs U.S. Nuclear Regulatory Commission GPU Nuclear, Inc. 475 Allendale Road P.O. Box 480 King of Prussia, PA 19406 Middletown, PA 17057 Ernest L. Blake, Jr., Esquire Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.
Washington, DC 20037 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 Chairman Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 Wayne L. Schmidt Senior Resident Inspector (TMI-1)
U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057 Regional Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Robert B. Borsum B&W Nuclear Technologies Suite 525 1700 Rockville Pike Rockville, MD 20852
OCTOBER 27, 1999 MEETING WITH GPU NUCLEAR, INC.
LICENSING ISSUES STATUS ATTENDEES Name Affiliation T. Colburn NRC/NRR/DLPM/PDI, Section 1 S. Peterson NRC/NRR/DLPM/PDI, Section 1 D. Distel GPU Nuclear, Inc./Licensing (corporate)
R. Knight TMI/GPU Nuclear, Inc./Licensing (site)
E. Fuhrer TMI/GPU Nuclear, Inc./Licensing (site)
Attachment 1
GPU NUCLEAR INC.
LICENSING ACTION ISSUES STATUS OCTOBER 27, 1999 HANDOUT MATERIAL USED AT THE MEETING Attachment 2
TMI-I LICENSIN(G ACTIVITIES - OPEN ITEMS LIST A.I I'C (0RVN )DE(SRIPTIION :N(; "FRA( KIN; A(CTION IIIsTOIRY /sl'II ' I'(U N. I'RI D)JD 94 -9 1X I Gil't IN responded to (i1, on 4 12 93 (C_3 1-93-2015). BIl
( ;Cllcrlc 'hetrno-lag 330-I Fire 9.4032 NRC requested additional infiormatlion in a letter dated 12!21/93 (C311-93-3292) ,192517 Mhl9-IPlant Barriers
(;[1.92-08 GI'1 IN responded to 12/21 i93 RAl on 2/ 10794 (C311-94-2012) ,196417 3 NRC letter dated 9/19/94 (C1 11-94-3237) acknowledged the 2/101/94 RAI response and requested response to sections of RPI response MA1 *110 deferted or were incomplete.
(WIPIN responded to 5(0.54(t) request on 12/05/94.
NRC letter dated 12/29;94 requested additional information within 90 in a follow-up to the previous RAI.
(WP IN responded to NRC Follow-up to the RAI on 3/29/95 (C3 11-95-2119). Response to certain sections that require NI-I and N PC agreement.
NRC/Sandia review oft ('1 I IN 3/29/95 letter resulted in RAI requesting a prompt response.
NRC RAI dated 5/25/95 ((C311-95-3261) requested information in 45 days regarding 3/29/95 (PIIN response to the previous RAl (PUN response to the 5/26/95 response to the tbllow-up to the RAI was submitted 7/7/95 ((311-95-2265)
NRC denied the exemption request by letter (6710-96-3018) dated 1/5/96.
NRC denied the 1994 2.206 petitions to shutdown all thermolag plants and tiled DI)-96-03.
(Gl JN/NRC meeting was held on 4/16/96 (see Meeting writeup 6710-96-3186, dated 5/13/96) to clarily exemiption denial issues.
GiP IN responded to ampacity RAI on 10/12/96 (6710-96-2336).
3-hr barrier exemption requests submitted on 8/16/96 (6710-96-2229) requested NRC review by 10/31/96.
G(IUN submitted TR-094, Rev I on 8/28/96 (6710-96-2301) which was to be Enclosure 13but omitted from the 8/16/96 letter.
(GMtIN submitted Thenro-lag evaluation/exemptions for I -hr barrier on 12/31/96.
(it'( IN responded to NRC 11/20/96 RAl (6710-96-3408) ors 3-tsr barrier evaluations and exemption request oil 1/3/97 (6710-9(-2412).
NRC issued SEP on 3-hr barriers on 07/11/97 for all areasxexcept FlI-F4-05 G(PUIN responded to 5/8/97 RAI (6710-97-3207) on ampacitV in a letter dated 07/31/97 (6710-97-2:343) which submitted the calculation on derating cable anipacity due to raceway fire barriers.
NRC issued RAl's on I-hour exemption request on (17/30/97 (6710-97-3347) ard 08/19/97 (6710-97-3378).
(il't IN letter on 08/19/97 (6710-97-2329) committed to upgrade Thenno-lag ir FH-FZ-5 to a 3-hr rating by 06/30198 3
(;PUN responded to NRC I-hour RAI of 07/ 0/97 on 09/08/97 (6710-97-2373).
Response to 1-hour Rid of'O0/19/97 (6710-97-3378) was submitted on 12/30/97 (6710-97-2489)
GPIUN provided consent to confinnatory order modilfving the license by letter dated 05/05/98 (1920-98-20232).
NRC issued consent to confirmatory order modifying license on 4/27/98 (1920-98-30237).
GPI IN letter dated 05/21/98 (1920-98-20225) provided additional conmmitment to relocate gas line in C13-FA-1.
NRC issued confirmatory order on 05/22!98 (1020-98-30295) modifying license to complete implementation ofTllenno-lag resolution.
,;Pt IN provided the final result%of revised calculationrs addressiig I-I. fire barrier seismic capability in a letter dated 09/28/98 (1920 98-20426).
Conference call with NRC on 9/29/98 discussed NRC a concern with gas line in CB-FA-l.
GPt IN submitted a response to NRC request regarding C13-FA-l ii a letter dated 101 14/98 (1920-98-20582).
(Ip IN submiihted commitment to inspect all barriers in a letter dated I1I25/98 (1920-98-20688).
NP (" irtrrorned xsalkdown of I-I lour exemption fire zones on 12/108/98.
(it' N ,biriittal dated 12123/98 (1920-98-20718) addressed I-Ilour tire zones BII-FZ-6 and CB-FA- I based on the 12108/98 "H( i-t',cd SIt on Ilhenr io-l ýig related anipacity derating issues on 1/22/99 (1920-99-30039) and closed TAC No. NIA3340.
0( i,,icd SI.R to I -1four barrier exemptions on 04/20/99 R
5 N1*( lonter dated'0 13 99 (1920-99-(30277) requested a description of the proposed corrective actions for zones AB-FZ-3, AI3-1Z-7,
.nd II 1. /-2 and 0orlirnfirations that the proposed corrective actions will be completed by 12/31/99..
(W' N lcttc dated 06102/99 (1920-99-20279) committed to complete l-Ilour upgrades in three zones by 06/30/2000.
NRC issued a request foi consent to modtif' existing confimiatory order on (16 21/99 (1920-99-30348).
(;Pllt N responded sith consent inra letter dated 07/01/99 (1920-99-20350).
NRC issued a second confinnatory order isodilying the license in a letter dated 08/11/99 (1920-99-30464) in response to commitments in (ill N letters dated 0(/02199 and 07'01/99 to complete final implementation ofcorrective actions by 06/30(2000.
S ItAl !S NRC IQ issue air additional letter to summnarize the submittals, identify the notification requirements if'plans change, and request notification of completion of'the modilications.
I uc-dr,( Uohtber 2(, 1999 Palge I A1(6
TMI-I LICENSING A(C"IVITIES - OPEN ITEMS LIST
(;PI;N I AC No ). 11HI FN(; "I'A(KIN(. ACTlION HIISTORY / STATUIS U
.'II,( ;t))l( " DI)ICRIPt*'ll'ON UAI0) (1GR
\1I9805 C I)egradation Of*CR I)l MRK 97056 NRC issued ( 1,97-01 on 041,01,97 (6710-97-:3155) whlich requested within 30 days a commitment to provide a response in 120 days
( 1.eici I1 Nozzles & Other RV 6Pt IN submitted a 30 day response on 04/30/97 (6710-97-2175) committing to tile 120 day response by 07/29/97.
( 1.7- I lead Penetrations GPI IN submitted the 120 day response letter on 07i29/97 (6710-97-2295).
NRC issued RAI dated 08/28/98 (1920-98-301502) requesting a response in 120 davs. GIPIN to respond to RAI by II 26!98 due GPItIN submitted a letter dated 11/12/98 (1920-98-20655) acknowledging NRC's agreement in a meeting with NEI to a 1 15/99 date for the RAI response, based on NlIl scheduled date of 12/11/98 for submittal of the generic response letter.
N FI letter dated 12/1 I/98 submitted tile generic response, including responses to 'TMI-1 questions I-5.
GPI IN submitted response to the 08/28/98 RAI in a letter dated 0)1/14/99 (1920-98-20737) which referenced tile NEI generic response to questions I-5 with the (;PI IN response to question No. 6 attached.
03/21/99 (1920 NRC issued approval letter for NEI generic program for VIII' nozzles. The letter it) NItl (Strosneider to Modeen), dated IRIG will 99-30216) stated that closure of NRC reviews ofthe plant-specific responses will be completed in the near term, and that a N1 tbllow which suniniarizes the stall's and industry's elobrts in addressing this issue.
STATI IS: NRC to respond by 09/30/99.
Mitigation F:unctions While (ilel 9w-1 I oss Of
( Iniventory & NIRK 98099 NRC issued G1, 98-02, "loss ()f Reactor Coolant Inventory & Associated Potential For loss Of Emergency by 11/24/98 only if the assessment klulti-Phlan I iiiergency Mlitigation In A Shutdown Condition, " which requires a documented internal review and could require submittal (Gl, 98-02 IFunctions While S/I) concludes that ECCS includes design teatures, such as common pump suction header, which can render the systems susceptible to comnnon-cause ftailure as a result of'events similar to 9/94 Wolf Creek event.
to voiding because the RCS (ill IN assessmnent concluded TM I does have a common pump suction header, but is not susceptible enter the S!I) cooling system betwecen the IBWST outlet and the pump suction. See GPIlIN System recirculated fluid does not 2
." signed offby G. A. Yockey, Engineering menmo E270-98-019, dated 10/01/98 (LAR 998099.01 ), "Response to Generie Letter 98-0 Ma.siero who called in no W. P. McSorley, and W. S Wilkerson. Reviewers were by Lan) Noll, Tom Basso, and (Steve Ku for) Dave coilitilets oil tile response it1einlo.
Shutdown and Conmmon NRC PPR letter (1920-99-30532) dated 09/30/99 advised (lPI IN of ai inspection entitled "Draitndown )uring ont the GPt IN intenial respoinse to (il 98 Mode Failure," tile week of 03/21 /99 through 03/24/99 by one Region I inspector to lbllow up
- 02. Similar inspections are planned tbr all PWR licensees using Inspection Procedure (IP) 2515/142.
STATI IS: NRC to review MPt IN internal response by TBI)
%l.\410 C Potential for D)egradation IMRK 98129 NRC issued (0I, 98-04, "Potential For l)egradation Of the Emergency Core Cooling System and the Containment Spray System Alter A\
( ,eriei i*-" on tOf Ct'cS & OS alter lIoss-Of-Coolant Accident Because OfConstruction And Protective Coating D)eficiencies And Foreign Material In Containment,"
Nfulli-Phlnt I I(W\ 7 14/98 (1920-98-30437) requesting a 1201day response.
(& 9X-0'4 pt IN submitted the required response ott II I Ii98 (1920-98-20605)5 S II I S NIRC I, to eviess (GPl IN response by 11 /3 1/2000 C
\t Its 'ii IKl NR( i*wcd, (I ')-02, "I.iaorattirv TIestitig of Nuclear-tGrade Activated Charcoal," oni 6/03/99 (1920-99-30357) wliicl requested
( ;I ')) 1{2 Since TMI- I is in Group 2, "plants in Nullhi- Plant Ic,.1-11w, d,'pCindCn on %%Inchol'ft ur groups is applicable lir thte plant as defined in iLe GI
( it, 99)-02 , ,olihihicl VS thit test in accordance widi a test protocol other than ASTNI 1)3803-1989," TMI-I is required to: I ) Submit a "th (d itsll iIi tile curnei TS requirement,; fbr each 1I SF ventilation system including tile specific test protocol, I, u I.hll)PI I hari i* tldif lhickniess. total residence time Pei bed depth. atd penetration at which tleTS require tile test to be u.i ii 2l Stibilit a I SCR rcleiencing \'STM D13803-1989 or alternate test protocol within 180 days and 3) Begin testing in t ii,l11.,
, \S I \1 I) 1803-1989)al die next required laboralor' sviurveillance test of a charcoal sample that is 60 days or more aller tic dfc .,I lie ( il , eopliacedie chaucoal with charcoal that has met the iequiirements of ASTFM 1)3803-1 989 laboratory testing N R( sii-,ld I I ')99-02 (rIrata) dated 08,23,99 (1920-99-30493) because of a typo: should be "lfthe systeit has a fhee velocity greater Ihlan I I10". ( us 10)") of 0 203 mis (40 itWii). thei the revised IS should specify the ace velocity."
S I \ I ' S (iPl 'N to suibiiit t lesponse 1tothe IH,and a TSCR by 11/301/99.
Plge 2 oI I, I ucsda. )clohcr 21,. 199
TMI-I LIC(ENSING A(Ci'IVITIES - O(PEN ITEMS LIST I C.('KI, (;
( 'A I ll(;( )l,% I)1;U RI PTl ) N IM N). PRI AC'TION IIISTORY / STAI'US
( tienlI Sctirnic Qualiticsatot of' ).11) NRC issued two Salt'vY Evaluation Reports (S,'Ks) to close (GI 81-14. See SIRs dated 0812/83 (5211-83-3255) and 04,27 84 (5211 tnlilt I l .\Xii iItai7 I eedivat Cr 84-3137).
M [III Pat I (;P iN to sutbnmit a suppltlementary response to GI. 81-14 to capture the reanalysis ,d)fl'OFW/seismic and SIl) ,x.' seisntic FF:W (S i. t1-14 \neistcIis capability' by 10;99.
I PI Pump,1111 Suction NIMK 970102 N RC l'xed question on the (G I' IN SI' oir leaving the cross connects open. The question related to whether a common mode fIlihlie MA..\1607 Sp*iteifi, \'tdneralbility 981O00 potential is created by maintaining the cross connects open. %..\59 3S 1111I GI'I.JN responded to question taxed to (GPIIN ot (05/14/98 itt a letter dated 7/17/98 (1920-98-20384).
Per Lic Act Mtg on (06/04/98, the NRC want.%to resolve this issue within the next couple of nonths.
(
Reference:
11: 98-02-03, ILER 98-09ý ANI) VIO 98-06-0111 NRC issued VIO 98-06-0 1. dated 10/15/98 GPtUN responded to VI() 98-06-01 in a letter dated II 12/98 (1920-99-20654).
OIPt IN provided a supplement to the reply to VIO 98-0)6-01 dated 12/24/98 (1920-98-20716)
NRC issued Reply to tie NOV Response in a letter dated 03/29/99 (1920-99-30162) with the NRC's position that a license change is still needed.
6 1ipI.N met with the NRC on 07/I 3/99 to discuss the proposed response to the NRC 03!29/99 letter.
NRC issued a meeting sumnnary lor the (17/1.3/99 meeting on 08W04/99 (1920-99-30452).
(GIPJN to submit License Change Requeest by 10/99 as described in the mneeting summary.
STATI' S: See TSCR 287 Phlat Rtelicl- RV' Weld Fxamn NIRK GIIt IN to submit request ibrieliel'tiom the 1989 ASNIE COD)E"requirement imposed by IOCIFR50.55a(g)(ii)(a) to examine 90'. of all Specific: ISI RV wselds during 14R (9/20(01) Requesttodemtonstrate impracticality regarding two of the eight welds which are, 900oaccessible using the tools available at the time of submittal. (Ref: IN 96-032).
NRC requested in 05/07/99 I icensing Activities Meeting that our letter discuss any potential alternatives to the examinations that are not practical, e.g., visual examinations, etc.
t SI'AT IS: (UlP IN to submit relief request by 11/30/99 requesting approval by 06/2000 Ptlant Relicf- IWI & IWI. NIRK GPI IN to submit request for relie l'rom the I (CFR50(55a requirements (61 FR 41303) to perform contatinment inspections in 1H2 C'ontainm~el/ nt,hpe,:ions accordance with time 1992 Edition with the 1992 Addenda of Section XI, subsection IWE. The NRC has approved this relief for the pilot Sptecific -IS[
IBW()( submittal, l)avis lBesse (Docket No. 50-346), in an SER dated 06/30/98. NRC requested in 05/017/99 licensing Activities Mlectnig that our letter meterence any other similar NRC approvals that have been issued for other licensees.
SI \ It , ill "-. ',, uItiit rlchtfrequest bv I I'1 5/99 requesttig reliefby 06/2000(
P1,l1 h,I t ,t .t ,1
- 4. I -,1 t 19'120 3030X). the NIRC requested additional infonmation regarding OTSG kinetic expansion area M199388 C 71
. ..t,t, .-, i ihted in (;Ph IN Ictets dated (08 08 97 (t 0 23,18) and 1I /26/97 (6710-97-2441) and requested a S, I !Ii , lit', ," piaIIttt I Ja cIe sail1tt lR.onciteri to he used i0 13R .
- ,. *,..* " ini, thicN 14s R \1 nI a lettet dated 1(7 1099 (I1920-99-20412) The letter stated that tPLIN intends to use I t i. that tted in 12 R hr the I )SG S( kineli expansion area exanminations, and that GlIUN will support NRC
-o.
1-11., .,tAci e:\ai ,I tci a although iic do not believe that NRC review and approval is required. The letter also a , -I,, \PR-T I X20. Rc istoni I" '"l'lncc MileI]sland (Generating Station OTSG Kinetic Expansion Inspection is.. i. t,lt .,I the MIR report that sias used otii12R examinations i ii,i,,t \IlT I X2() Re.ioion I oin (1820;99 (1920-99-20448)1
" . &t ht its i t ited I"- ons rloin the NRC during a conference call ott I0/I 2/99 in addition to providing the Tech Spec i .tI it ,t* ,-h,1 ilid [)i101tIo heating up above 250 F. 'l'he NRC said they would let us know if anything else is nedded
"'I n , it a ( oiccted ('Copy ifth (17 ;30199 RAI response letter in a letter dated 10/22/99 (1920-99-20568) with a paragraph
,I ... itl I tic i i,-,cd outl pat agiaph had mentioned additional conservatism that was later found did not exist; the response is I NIl S \ 1I io Icl (lit N kno\i, if'antthing else is needed subsequent to the conference call on 10/I 2/99.
I uc.ýda%. ( ),lol',*r 26, 1999 Pagc ; ittIi
TMI-I IC(ENSING A(C"TIVITIES - OPEN ITEMS LIST C'.VI'E(;)RN DSllRRIl)N P IN( "I'RA('KINI; A(C'TION HISTORY / S'I'ATUIS I M" Nob. PRI TMI-I lic" C-ont~ainmlent NIRK GPI IN to submit I'SCIR to allow air lxck doors to be open during fuel movement based on oifisite dose consequences of a tfuel1 handling (Chg Rcqucst Requirements D)ol ig accident using the newv source terms (NI RI'.i-l1465).
No. 21.9 Refuneling STATt IS: ( )i hold pending NRC aprooval ofthe I'PR TR-105909, "GCeneric Framework for Application of' Revised Accident Soiiurcc Terni To Operating Plants." See draft "Proposed Rule Package - Proposed Amendments to 10 CFR Parts 21, 50, aid 54 Regarding I Ise of an Alternative Source 'ernn at O)perating Reactors."
I M,,I-I Lic Mist Section 3&.l Vl ,K 97033 GMl'IN submitted ""SCR-262 on 0-1/01/99 (1920-99-20681 ) requesting changes that include RSTS improvements, claiification of MA 5185 I1 (Chi, Requic't ITupi uovciicrits existing specs, and changes in sampling frequency and sampling requirements.
No 262 NRC issued a partial denial of'l'SCR-262 in a letter dated 08/06/99 (1920-99-30461) regarding the request to pennit continued I11il operation, without violating the "Ss, if ll1'1 is operating during all emergency cooldown rather than invoke 10 CFR 50.54(x).
STATt IS: NRC target amendment date is 12/99 (NRC acknowledged GlI IN request for the amendment prior to 131 and will work getting it out earlier if time permits).
I1 1I-I I.ic Shutdown Ill IR AWM 98111 GPUN submitted TSCR-265 oni06,04/99 (1920-99-20390) to revise the shutdown decay heat requirements that NRC character ived in C t lhgIRequcst Capability Requiieicnits IR 97-09 as non-conservative.
No 265 NRC requested that (1Pl IN submit a supplement that provides certain background during a conference call on 10/05/99.
S'ATI IS: G11t IN has requested a target anmendrnent date ofl 2/03199.
TINI-I ILic MSI.B Reanalysis & RCS l)JI) 98076 GPI IN submitted TSCR-272 on 10/19/98 (1920-98-20(21 0)-to restore RCS activitN level up to 1.0 pCi/g based on MSI.B reanalysis. NIA3951
('hg Request *\ctivity 1,0 1(.'i('g NRC issued Federal Register Notice on I / 18/98 No, 272 GPUN submitted a letter on 02126'99 (1920-99-20052) referencing the updated control room doses to address the NRC issues ii an enclosure to TSCR-274.
NRC issued RAI on 07/08/99 (1920-99-30395).
(i[ IN responded to the RAI on 09/02/99 (1920-99-20447) Polestar proprietary and rion-proprietary.
STAT IS: NRC target amendment date is 111)
"I I-I I.ic Sicense Clarilications VIK 98110 (Gl1t IN submitted 'TSCR-275 on 05/13/99 (1920-99-20(387) to iiclude clarifications and other changes due to GPUN organizational M:A5455 13 Clug Rcqucst changes. Included are changes to tie Baises for Pressurizer Code Safety Valves No 275 STX It 1S: NRC target aiiendiment date is 11!99 TI-I I t I\1I I I I,cn, lIuiilccr to I tI) 9X1 S2 NRC' issued a -uilruiiiai of')/17198 ieetiig on 10051,98 (1 920-98-30587). NI 13137 0 \
Chg I?cIuc, \i ci ( ;,i1 (;P( 'N \iiiti (cii suililiti a I0CFR50 80 license tranuster application oil 12103!98. NRC review and approval was requested by No 279 (0.1I 99 NIR( i.ucd R \I ,ln 12 17 ')8
\ R( Is'icd I cde iil Register Notice oil 12,21,98
'I'l \ -uluuitltd Icspoine it) RAI on 01/I 1i99 (1920-98-20732).
I, ,'i .I cii is & Hoc.kinus subiiitted siupphl.oental inlrmination on 02(04/99 (1920-99-20072) oil behalf of'IP, IN and Arner( en.
\ IN( i.cd an ( Ii dreed fill 04 12,99 (1920-99-30193) approving transfer oflthe license fur T'MI-I from GIPUIN to AmrerGien and iloll ii Thlieo1iloriliong anirendnient.
S I \ I "* (; I' 'N :\,nril en to submiit final notification of sale closing date, receipt of all other regulatory approvals, and evidence of Pall 1410 insurance is thin 7 days of'the closing date.
I[, lI- I Ic I Is,frigcii C<cciumc IK 9(,0"-1 Note: I SCR -280 involves the I lydrogen Recombiner issue as broken out of TSCR-255 N191522 Clig Request "p1cc iticationis hI , ')w(( (1 N RIC'issiuf R.I (ated 116dtt II r97. (6710-97-3262) which requests submittal of calculations to justify the change.
No. 2810 I'SCR-2s5)
ST\ I IS GPi IN to submit TSCR by 1105/99.
I ucsdas . )cIiobci 26. 1999 P~agc 4 ol'6*
TMi-I I(IKNSING A(CTIVITIES - OPEN ITEMS LIST
( ATI (()RY DESC('RIPTIION F' I RACK'ING; AClTION IIISTIOR / .'AT'I IS I \ ('N(). i'RI I \ I- I Iw \ux Stean Systl I Piiping YN 97o(62 H' ýN submitted Iicense Change Request No. 281 on 05/20'99 (1920-99-20140) for approval of the Conservative l)etenrninislic t 'h Rcqucst scisniu ('apal',ail.t Failure Margin (C'I)FlN) analysis fImseismic verification ol'the Auxiliary Stearn System piping. The proposed seismic evaluatiln No 281 .\nalvsis mcthod, CI)FI . sas developed hy I'PR and has been used at a number ol'other nuclear plants. .,s requested by NRC, (;PH N subnittial referred to similar NRC approvals lot othei plants.
ST I'S:t NRC to coiiplete reviewh Ity01/3112000.
I MI-I II PLiht (igani/alion Title l}.lt 99077 ( if IN siibmitted ILicense Change Request No. 282 on 0)6/ 1,99 (192(1-99-20200) to revise the I)irector ()&%N, Shill Supei isoi.
(fig RC eiCtlct Radiological Conlrols/Salft I)irectoi, and Industrial salety and Health Manager titles identified in TMI-I Technical Specilicat ions.
No 282 S'I Vlt IS: NRC target amiendnment date is 1 P99.
I MI- I Lic Degraded Grid U'V Relay W\(II 9909o GiPI IN submitted I'SCR 2813 oii 09,20/99 (1920-99-20295) to revise the 4kv Engineered Safeguards Bus I Indervoltage Relay ])egiadcd 112
('fig Request Calibration I:i queici and Voltage calibration to be perfonned at an annual interral rallher than refueling interval and a bases change to revise the degraded voltage Ni 28 "etlpoinl "'Iolerance relay "as-letl" setpoint tolerance from 3700 v -.53%. 10.35%, to an "as-lound" selpoint tolerance. "he latest anah sis identifies the need fbr earlier operator action to prevent separation from the grid for some conditions and idenitifies additional saftly related compoients that could be operated outside the normal voltage tolerance bands. The justification fbr operation of the components outside the normal band is desci ibed in this request.
S'ATI I: NRC target amendment date is 'l'IT )
N1- 11 MI Adopt STIS iniplace of I (GMGr Gl'UN to submit "'SCR to adopt SI'S in place of rI'S die 1-Ir shutdown requirements ii TMNI-I TS Ill
('hg R~equest II 'T'S Shutdown No. 284 Riicquirenients S'IAll. IS: ( )n I told
['IlM-I lric Changes to Clar il'N' AWM'\ 99109 IlI 99110 011 IN submitted License ,nmendinent Request (ILAR) No. 285 on 06/29/99 (1920-99-20339) to clarilf, the authority to possess MI5X')71 No.g Request :uthority to Possess radioactive materials without unit distiiction, so that alter the trasfer fo the 'I'MI-I license to Amerl-en, radioactive materials maN NI NAl{1,4 No. 285 Radioactive Malterials continue to be moved between the 'I'tl-I and TMI-2 units ats they currently are 'llhe letter requested approval on an expedited basis to Withlout U nit l)Dstrinction allow uninterrupted continuation of past practices, It was requested that this change be made etffctive upon the ['fI-I sale closure and Ii ansfer date.
Nofe thit a corresponding MI-2 license Amuendiment Request No. 77 was also submitted oil 06/29/99 (1920-99-20335).
NRC issued Federal Register Notice for 'Itl-I 1l'SCR-285 onl 07/12/99 NRC' issued an RA\I on 08/10/99 for TNI-I ILAR No. 285 (1920-99-30450) and 'lTI-2 I.AR No. 77 (1920-99-30458).
{it't IN rispunded to RAI on 08/27/99 (1920-99-2(0474) for TNII-I lor TNII-I and on 0)8,127/99 (1920-99-20476) Ibr ']'MI-2.
NRC issued Federal Register Notice fbir TII-2 TSCR-77 on 09112299.
ST VI 'I S NMRWiiget amierndinent date '1II)
T I-NtI Ii.w \IR 1' Ii ('l i' itil'liii, I icensc ( 'fhange Request to revise Ilech Spec ITafble 4.1-1 itemn29, II1 1 i & I.,1 1 Flow Irnstrument Calibration frequencv
.'hig Reutlie-t I,,I ii liii' ,, l"" I I* i Iii) Ns '1:'( 2.' months). 'Ilese instruments wcre not included in previous similar submittals requesting a 24 mo No 2811 - lIt ii cI iiivii) (be. lti.e the impact oil sys'temi operability. was not recognized at the time (this issue was discussed in I.ER 98-01)
SMI- I IC Nlikeu I(nk I. m, I,' I,, xuhm il " Nt'I R (\ 121'29 99 to add Makeup Tank LIevel and Pressure I nuts as described in meeting with NRC on 07'13 99 M. 5935 (
'lug R fqueist t' xIii unit, N Itt lcctiii su-rc mRI. ( 1920-99-30452) dated 08(104:99.
No 287 S I \NtIS Wl't N to sufbruit License Change Rcqirestl I V 10/29,i99.
TI I- I (ic uhaucoal !:itcl I c'Iilgk MNR '")' 1 17 I hlsl,action is a continuation of the action ii response to (Gi, 99-02. C (Cfhg Requies (61I. 99-02 ) (WI ýN to subuini 'I SCR ti ievisc the test standard to AUSIMI ID380.3-1989 by 1 I/30/99.
No. 2 X9 I ucsdai. ( )chiilc 2(,. 1999
TMI-I LI(CENSING ACT1IVITIES - OPEN ITEMS IiST E ;1'I N
'KIN(; IM. , No). PRI EN( TRA(
( AI'I'G(O)RY DElS( IMlPTI()N A(CTION IlIS'OTORY / SIATIS (I',l-I tic [SIF Sy stent Ieakage and (iNfl{ ,\NI 2 15 (lioi n 'ISC1R-274) expires at the end of'Cycle 13 due to NRC expectation of the resolution of the generic C13VS infilitation
'fig RCeqinest CRllabitability issue in the neai termt "lhereklre the NPt' is iequiring that a license change request he submitted in contfilmance with the resouluion of No 29(0 Resublittal that issue at least 6 mo prior to the end of Cycle 13 (est. 03/0 Of1 ).
STAIAl IS: (G IN to sutimit "IS('Rby (./0] /99.
S)TS( iTube Inspection ,IR K {PIN to sulniit 'I'SC'U fbi ptinianent ( )'I'S( "'ube Inspection Criteria after Cycle 13.
T I -II Iic (fig Request Criteria fbr 141R and No. 291 I leond S'fAlI IS: (i1't IN to submit I SCR by 06,2000.
BI INI- I I Ic Missile Shield Renmo'al RTZ 97049.03 (il(l IN submitted a letter dated 07/12/99 (1920-99-2(0254) requesting a mneeting with the NRC to discuss reconsideration of the Opt IN fhgRequest request for missile shield removal denijed in NRC S'R dated 09/16/98 (1920-98-30541). In a conference call on 08/10/99, it was No XXI concluded that a success path, if one exists, is to prepare detailed quantitative detennmistic flaw tolerance evaluation analyses to support a submittal in accordance with R.G. 1.174, "An Approach lbr I Jsing Probabilistic Risk Assessment In Risk-lnlbmiled l)ecisions On Plant Specific Changes to the LIicensing I asis."
STATUS: (Ill IN to develtp an adtion plai with preliminary results and schedule a ,neeting with the NRC to discuss the proposed approach for iequesting deletion of requirettents ftor the missile shields.
i,1 TMINl-I Lic PfT imitts YN (il'tIJN to subtit TS('PIto revsis fl-f imitts fey otid 17.7 fFIPY current limits which expire in 3rd quarter 2001. Note- Generic icense
('hg Request Renewal Program reports tIAW-2274P-A. "Fracture Nlechai/nics Analysis Postulated IUnderclad Cracks in 13&W Designed Reactor No. XX2 Vessels lbr the period of Extended (Operation," was issued in August 1999 and IIAW-225 IA, "l)ermonstration oftthe Management (it' Aging [Fleets Ior the Reactor Vessel." w+vas issued in August 1999.
STATI IS: OPtI IN to submit TSCR by 09,'0 1 /2010.
t MR K (i ). IN to subrmit L icense Change Request to extend the time after a I.( )CA for establishing continuous indication olcontainlnlent TINI Lic I lyfdiogci Moulitirs Clhg Reiquest hydrogen concentration.
No. XXI STATI IS: (WPIIN It suhril Lticense Change Request by I1/0I/99.
GiM IN to submt it a ILicense Change Request fbi approval of the revisionit t I[:SA\R Ch'apter 14 accident analysis based on the Chapter 1.1 TNII-I 1.ic I S: R\I('fhaptei f-1 t t!-ladcS, t Ipgradc eflcrtl
('hfg keIfc'tt Nio XX4 S IATU . Sý G IUN io sulalmit request (SIFI*R) by 12/31/99.
(,il' N to iuhmit 'I SCR to allow Re-roll Repairs for potential use during the 14R (Otutage in 9/21001 TMI-I I'lc MlgIK Cfig Rcquciil No XXS S I \ II ; Ifil I)
TINI I~l I,'I \ t,, 1timt I'S 'R to chang,e I ch Spec and Bases for Air Treatietit Systenls (Control Bldg, A&I"Il3, ANDI)FlI1B fSF) testitig 13F It I Li
ll I ,, x "I I, I a Chg Request R, ii.1 -,ittt..ddiall "'Prlposed Rule Package - Pioposed Anmendments to 10 CFR P rts 21, 50, and 54. Regarding I Iseof at til 17 o I No. XX6 \IictiiLI.ilc Si*tU2 Tt-ci el I atOp<1atmiIg Reactors."
S I \f IS (Oin I tfIl (l pendinIg resofItuliot oif NRU' proposed Rule Change.
Page 0 oif I'uoda\. ( )ctolicr 26. 19 9 1)
I Lie-,&I%. (), 1"bel 2(,, 1999 GPUN/NRC LICENSING ACTIVITIES LIST - ITEMS TO CLOSE
( att'gon I)E;S( RI,'H[ION EN, TIRA( IN
(;I'T KIN( A("I'ION IiI.8'i'(RY / STFAT! IS 1I.\(' N(). PR[
( ;ciW 1CMLlti Degiradation ()f Steani NIRK 981033 NRC issued (1, 97-06, "D)egradation ( )',Steam Generator Internals,"' on 12/30/97 (61.20-98-30007) which requested a M.\0954 Plant (ifl. 97-06 (kiierator Internials response within 90 days.
(;Pt IN Responded to (I.e 97-06 on 03/3(W98 (1920-98-20154).
NRC issued a letter closing the TAC for this issue on October I, 1999 (1920-99-30553.
STATU S: CLOSEDI)
( ;crier ic Multi Year 2000 Readiness "Y'N 98093 NRC issued ('I 98-001, "'Year 2000 Readiness of Coniputer Systems at Nuclear Power Plants," dated 05/11/98 (1920-98 N\IA1899 C Plant (GlM 98-01 30290), which requires a 90 day response by 081(09/98 and a final status by 07/01/99.
(Pl IN responded to 90 day request on 08/06/98 (1920-98-20392).
NRC issued GI, 98-01, Supplement 1, dated 01/14/99 (1920-99-30075) which piovides an alternative for the response doe 07/01/99.
GPlIN responded to Supplemient I on (17/01/99 (1920-99-20275).
NRC issued NIREG-1706, "Year 2000 Readiness in U.S. Nuclear Power Plants," as of 09/01/99 (1920-99-30516).
NRC reforenced N1LRIG-1706 in a letterdated 09/23/99 (1920-99-30518), acknowledged the GtlUIN 07/01/99 response to (1l 01, and requested a letter documenting when the balance TNMI-I work to resolve the Y2K issue.
(il'[ IN submitted a letter dated 10/01199 (1920-99-20520) confimning that the software systems and DICS had been rernediated and the Y2K readiness progrtan at TNII-l has been completed.
A conference call was held on 10 /05i99 to discuss the 61t IN final response. No ftrther actions are planned.
STATIIS: CI .OSID Plant Specific Coiitiol Room Ilhi, roid l)Jl) NRC letter dated 09i24/97 (6710-97-34339) requested analysis ofscontrol room thyroid dose. NRC SER on NIRL-G-0737, NI...02.1( BI (R Tl'hyroid IDoe l)ose E.svaluation Item 111.11.3.4 dated 081 4/86 (5211-86-3215) stated that NRC will reevaluate thyroid doses at a future date alter completion of the source terni study. Although new source terns are not yet completed, NRC letter dated 09/24/97 requested analysis of control room thyroid dose for compliance with GI)C 19.
GP[ IN submitted control room thyroid dose evaluation on (13/24/98 (19201-98-20145) as discussed with NRC in a meeting on 12,12/97 (see meeting summary 61,20-98-30065, dated 2,2/981 N RC meeting held on 05/27/98 to discuss evaluation methodology, assumptions, and results (see meeting surtunary 1920-8 0 177, dated 0 101 ,98).
( W1 ýN qubmitted additional iiitorialion oil meteorology, testinspection and evaluation ofrad setpoint on 06/19'98 (1920-98 2(122)
W1 'N milhniied polestai report on.Nll A I-SF leakage partitioning on 1/ (10698 (1920-98-20561 ) to address concern on
\Xt( ( )N amid2-Nignia assuniption.
\ RI( 'miter cilaM Il on II (09,'98 and 12/15/98. and NR . RAl dated 1/201998 (1920-98-3071(0) identified ARCIO.N
[i IId'lliýý' anid Poflcslaij parliliolning non-conservalive.
I11Im,,u Ilis icii elmcdmIr Cle 13 in Aiiuendtient No. 215 based oln (iPI IN subnmittal oflTSCR-274.
I \ II \ (CI (()I..I) Sec 1S(CR-290 tilt resolution of this issue for operating cycles following Cycle 13.
"I N lI .c 0w , RcIillol *iuil,,'ii c..Ii I)II) 1ý10 (ý \, t ainlcaumlerred li inn( ;cnemic NIulti-Illant ( i, 86-10. MI\39 N..A Request No. 248 sjmcc. W1 N Sulunuitted "I'SCI-248, R emote Shutdown Tech Specs, on 10/19/98 (1920-98-201 83).
N R(Ui,,ed I ederal Register Notice on I ]/I 898.
N i' sued R A\ on (.17I 2199 (1920-99-30435).
( lIV'N fesponded to R.Al oii 08/19!99 (1920-99-20438).
NR(' issucd A.NI-2 10( on (19,22,99 (1920-99-30517.
SIlATI IS: CIOSEI)
Page 1 of 3
GI UN/NRC I.I('ENSING ACT'IVITIES IIST - ITEMS TO (CIL)SE EN(; 'I'l¶\( 'KING A(CTION HIIST(ORY / Si'AIIIS I Mt No. I'M
( ite&giu' I)IS( 'RIP'ION
'I M I- I 1.1c ('lI NIII\ I"(','S AnaIsis (MG 98 159 (GII IN submitted 'I SCR-274 on 2/02 99(1920-98-20522) to increase ".S 4.5 4 from 0.(, gph to 15 gpli lbr accident NIA\02.1 HIl recirculation leakage based on a revised NIIlIA analysis and new control room habitability evaluation updated since the NI.X)2-16 Pcquuc-, No. 274 03/24/98 subnmittal to relled a 3-sigma approach to X!Q determinations aind point-source contaminant releases as opposed to dispersed source releases. Included were the changes to die Control Room Habitability Evaluation to address the NRC's 11/20198 RAI for the (GItIN CR Hlabitability submittal dated 03/24/98.
GPU N met with NRC on 77I 3/99 in Rockville, Nil) regarding proposed changes to the ATOG piocedures for operation otlic BS System which requires NRC approval of'TSCR-274.
(Pt IN submitted a suipplement to '""SCR-274 on 07/29/99 (1920-99-20427) to restrict applicability of this change it) one cycle only as requested by the NRC in a conlerence call on 07/27/99.
NRC issued a 08/04/99 (1920-99-30452), file no. 98046, summary of the 07 13/99 meeting in Rockville, Nil) where '"1CSR 274 was discussed.
NRC issued AM-215, dated 08/24/99 (1920-99-30487) which expires at the end ot'Cycle 13 due to NRC expectation of the resolution of the New Source Temi ixsue in the near temnn. 'lierefore the N RC is requiring that a license change request be submitted in conlomuance sith the resolution ofthat issue at least 6 mo prior to the end of Cycle 13 (est. 03/01/01 ).
GPUN submitted an errata page on 0901 /99 (1920-99-2(0479) for reissuance by NRC of a corrected copy of ANI-215.
NRC issued die eirata to ANI-215 in a letter dated 09/23/99 (1920-99-3(0521).
NRC issued an errata to the its Safety Evaluation for AM-215 on 10/14/99 (1920-99-30576)1 ST..VIAIS: CL(OSEDI)
TII-I I.ic. Chug ()1 SG' Total l'lugmiug l)Jl) 98195 (PLIIN submitted License Change Request and supporting analysis on 12.03,98(1920-98-20669) requesting NRC apprioal to MAI-*0 I Request No. 279 Limits revise the total plug limits in the UIpdated FSAR 'Tisissue is related to the license transler (requested by AunierGen) and NR.
support is requested to ticilitate a resolution of this issue by 4/15/99.
NRC issued Federal Kcgister Notice on 12/30/98.
GIPUN notilied NRC in accordance with I 0CFR5O046 on (12/0(5/99 (1920-99-20053) that FTI's L31.tOCA analyse*
supporting current plant operation that have noncoiservative peak clad temperature predictions. The letter stated that reanalysis will detemiine the alfect on proposed I lIR and PCTs reported in TSCR-279.
NRC requested additional information on 03/10/99 (1920-99-3(0137).
GPtIN submitted a response to the RAI on 03/26/99 (1920-99-20088).
(WI IN submitted a response on 04,16/99 (1920-99-20184) to requests friom a 04,06/99 telephone discussion.
NRC issued RAI on 05/06/99 (1920-99-30273) on EFW Ilow requirements.
(;t 'N su'Nuiutled a response on 05/07/99 (1920-99-20222) to a request regarding instrument error (It'[ oinunuicd the FII ECCS revised analyses lor 1.13l .OCA and SBI.)CA per IOCFRI50.46 on 05/12,99 (19210-99 I
,I , t, ,L.td 0 21 99 (1920-99-20269) responded to "FWRAIL PI'I I, ii. ,t,d t ,It -I99 (19211-99-20280) revised P'CT and I.()CA I.I R limits lbr flow mixing vane issue.
,," Ii - tahd qI m. I
- 99 ( 1920-99-20.316) advised NR(I oilcompletion o1'F:W calculation and design verifications.
, m,. 2') 99 1 1920-99-20 112) provided rcsults of the revised EFW calculations.
S. ,,~ I,.,,, \mendincnt No 21 .1 )in0O 19) 99 (19201-99-30468).
,.. ,.,. ,t ilii.s ,hii oift -oniilct iI IoI: W S puii p lests on October 211 1999.
ion tLii, IdI 1')
' 192(0-99-201) ) prosided the nol iication of'successful comtpletion ofI"EFW pump testing
. . \ X) 1 At "SI kI \ ( I()\,I I)
Page 2 ot 3
(WIUIN/NR( IICENSIN(; ACTIVITII'S LIST- IFEMS '1O CLOSE
(;I'I N (Catg*,r'y I)I Ns(RI 'I' 0I(
)N SIRA( KIN(G A( lION IIIS*T)ORY / SIA'II-S I VC No). PIH I Il-I Ii-( lhg I ;se olR, 1 61 D)arnping 1.I1) 99097 G(M jN to submit a I. icense Change Requi-st to revise the design basis for the pressurizer supports as CurrentI ly desciibed in tie Ilqucst No 28X %alies for Piessurizer T1II -I U IFSAR. :\pprova I of the aialy Isis will avoid a modificat ion that would exceed $200K an)d result in approximately 6-Il0 Supports man-i cn additiona I radiation exposure if installed. GPt IN submitted a description of the proposed analytical approach Io Fali itate preliminary discussions with the N RC on 08/12/99 (1920-99-20449)
(;'t iN is, installing the modilication and this action to pursue the analytical solution is a contingency in hie event ofil'poblems installing tlhe modification.
Pressurizer Support Lugs were modilied during the 13 O)utage Under Modilication I)ocument (NI)-I 14 18) compelted on
- 10. 17/99.
SITAT IS CANCEILLED)
Page 3 of ý
Meeting Notice E-Mail Hard Coly J. Zwolinski/S. Black E. Adensam PUBLIC S. Peterson PDI-1 R/F D. Hood D. Hood P. Tam OGC S. Little ACRS OPA Receptionist (OWFN and TWFN)
M. Oprendek, Region I M. Tschiltz cc: Licensee & Service List PMNS (Meeting Announcement Coordinator)