ML20092A409
| ML20092A409 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 02/03/1992 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20092A414 | List: |
| References | |
| LCR-89-13, NLR-N91144, NUDOCS 9202100102 | |
| Download: ML20092A409 (8) | |
Text
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IILR-119114 4 i[B e 3 IE Referencot LCR 89-13 U.S. liuclear Regulatory Commission Attention Document Control Desk Washington, DC 20555 Gentlement REQUEST FOR A!4EllDl4EliT FACILITY OPERATIllG LICEllSE llPF-57 IlOPE CREEK GEllERATIl1G STATIOli DOCKET 110. 50-354 Public Service Electric and Gas Company (PSE&G) horob'( transmits an application to amend Appendix A of racility Operating Licenso 11 0. IIPF-57 in accordance with 10CFR50.90.
This amendtient request will climinate the main steam lino isolation and autoaatic reactor shutdown functions of the main steam line radiation monitor in Technical Specification Tables 2.2.1-1, 3.3.1-1, 3. 3. ;.- 2,
4.3.1.1-1, 3.3.2-1, 3.3.2-3, and Bases Section 2.2.1.6.
A description of the requested amendment, supporting information and analyses for the change, and the basis for a no taignificant hazards consideration dotormination are provided in Attachment 1.
The Technical Specification pages affected by the proposed change are marked-up in Attachment 2.
WehavedeterminedthatthellopoCreekfacilithisspecifically bounded by the assumptions and justifications
.n General Electric Company Licensing Topical Report, 11EDO-314 00A, "Ea f ety_ _ Eval uation ipr Eliminatino the Boilina Water Reactor liain Steam Ling J.golation Valve Closuro Function and SCRAM runction of the Main Steam Line Radiationjignitor". and a DWR Owners Group lotter (DWROG 89-31) which provided answers to specific liRC questions regarding the topical report.
The liRC has issued their Safety Evaluation Report dated 14ay 15, 1991 accepting this liEDO document for referencing by licensees in their auendment requests.
Upon liRC approval of this proposed change, PSE&G requests that the amendment be made offective on the date of issuance, but implomontable within 100 days to provide sufficient time for associated physical plant modifications and amendment-related j
administrative activitics.
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92oa:00 02 920203
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FEB oa Hs2 Document Control Desk NLR-N91144 1
i Additionally, pursuant to the requirements of 10CTR50.91(b)(1),
PSE&G has provided a copy of this amendment request to tho Stato of New Jersey.
l Should you have any questions regarding this request, we will bo l
pleased to discuss them with you.
Sincerely,
,/
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Attachments Affidavit C
Mr. T. T. Martin, Administrator USNRC Rogion I Mr.
S.
Dombok USNRC Licensing-Project Manager Mr. T. P. Johnson USNRC Senior Resident Inspector Mr. K..Tosch, Chief, Bureau of Nuclear Engincoring New Jersey Department of Environmental Protection i
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REl": HLR-N91144 STATE OF NEW JERSEY
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SS.
COUNTY OF SAIIM
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Stanley LaBruna, being duly sworn according to law deposos and says j
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I am Vice President - Nuclear operations of Public Servico Electric and Gas Company, and an g i, I find the matters set forth in our letter dated IEB ' '
concerning the llope Crook Generating Station, are true to the best of my knowledge, information and belief.
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$fM" Subscribed and Sworn to before me day o f _2r /m __, 1992 this O
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Notary thablic gf He'w Jersey CLf2ALIETH J. KIDD Nowy Putile of New Jersey My Commission expires on 1% Conmwan Enoves Antd 25,1005
Pet: ILH 09-D ATTN 3 M NP 1 11DLW12tl1X1ELGLJilIEU3fATICRLNilLIVGILOWG l
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9 lioldill) OLAICE '1D 'll!E 'III3HICAL S11I'IFt.CATIOti FACILITV 0113&TI)G IJO2EE N11'-b7
'lDIE 002% C1N13RTI!C UTATIO4 IIXM!r 10. 50-354 reti ICR 89-13 IIIQUIT10LQE_lUlLQWG As shown on the mrked-up 1bahnical Spccifications pages in Attactront 2, charge Tbchnical Specification Table 2.2.1-1, Lunes Sections 2.2.1.5 ard 2.2.1.6, ard Tables 3.3 1-1, 3.3.1-2, 4.3.1.1-1, 3.3.2-1, 3.3.2-3 as follcvs:
1.
InhlgL2a'h.1-1 Delete IU4CTIORL MUT 6, "nTin Steam Lire Radiation -
liigh, liight" by inserting the rhraso, "This item intentiomlly blank" ard ren:r/o footnote "4" (rtgardirrj hydrogen injection test).
2.
11Nss,Jgygt;191LLW Delete the refererce to high steam line radiation.
3.
iE.cs Soctigtll h L.ld Ibleto itm 6 on page B 2-8, "Kiin Steam Line Rsdiation - liigh" by insertirg the phraso, "This item intent 10mily blank" 4.
Table 3.3 l-1 Delete luJCrIORL unT 6, "Msin Steam Lino ludiation -
t liigh, liigh" by insertirg the phraso, "This item intentiomlly blank", ard replace ACT1015 (which is associated cnly with IU3CTIORL UlGT 6) with a statement that "This AC1!Of is delettd" (which will mintain the correct ACTIGi numberirn in the Table for the other IUJCTICtRL UllrIS).
5.
Table 3.3.1-2 Delete FUICrlGML Uli1T 6, "Msin Steam Line RTdiation -
High, liigh" by insertirq the phraso, "This item intentiomlly blank".
6.
Table L'L LI.J Delete IU4CTIct1AL GIIT 6, "Kiin Steam Lire Padiation -
High, liigh" by irrertirg the phrase, "'Ihis item intentiomily blank", ard, at the crd of the Tiable, replace footroto (1), which is ansociatal cnly with IUICTIaiAL UlHT 6, with a statenent that "1his ACTIGi is delettd" (khich will maintain the correct ACTIQi numtering in the Table for the other IUICTIQiAL Ul4 TIS).
7.
Table 3 E -1 Mxiify the column titlcd YALVE ACI\\B11W_G[GM OITPATTJ)E SlGJBL for TRIP IUICT1013, MATil STEAM ITliE_Jf&lAT1W AS IV11DWS FUICTIQi 3.b. - delete "L", leaving only valve group 2, ard charge the requi.rtd AC170!i 21 to ACTIQ 128, 8.
Takle 3.3.2-1 Modify the column titicd YAWOS_C1MED BY SIGBL for TRIP IUJCTIQi"), 1%IN STEAM LIIIfa_If41ATIW As rollrus:
IU3CTICtl 3.b. - delete "l_LOS_Al72yph ", leaviry only valve gtw p 2.
to road Tablg*3.2-3, Modify the EDSist1SE TIME for 'IRIP_J1ETLotL1dh 9.
"$13
- ". This elimimtes the responso tim ard (*) notation for the MSIVs only.
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IMDLIMUllllLQWG Flimimtirq the min steam line raciation ronitor (milM) isolation of the min stem lines ard autumtic ruactor shut 4kun featums, as descritni in the IMI CVneni Grutp licensirg tcpical wrort (L3R) NIID-31400A, dated July 9, 1987, the USimC's Safety INaluation Eerort (SIR) for that dcxwent, ard in this rocpest will tenult in ratocni totential for unmoossary reactor rhutdcuma causcd by spurious MSUM actuation trips and will incrmas plant cperatiorul flexibility.
J1 FRY.lCATICfLLUUDi!LQWG
'Iho Imc staff has concitded that rutmal of the milN trips that autcrutically shut dcun the twetor ard clcre the mIVs is anceptable arti that Licersing Topical Petort (L3R), IRIO 31400A my be referavxd in su1 port of our amen 1 Tnt request prwided thatt the assunptions with twjani to input values mde in tno generic amlysis of the IIIR are tuudity for the plant, reasomble assurance that significantly incroaral radioactivity levels in the min steam lines will be expecliticusly contrullut to limit toth cocupaticrul ard envirurental rulcases is prwidad, ard the MSIIM ard offgas radiation nonitor retpoints are stanianiizcd at 1.5 tims the nitrcgen-16 backgtvurd dcre rate at the monitor locations ard should either or teth exoood their alann setpoint, the tractor coolant will be pnrptly sarpled to detennino activity levels ard the possible rox1 for additiomi corrective actions.
Attachment ; addresses IEl%G's ctrpliance with the above corditions which, ocupled with our Tarticirution in the IHOG MSUM activities, justifies our ure of the subject L3R in support of this recpect.
Whilo rot spccifically addressed in the I:nt, the min steam lino drain valves, IN-F016 (Inboani), IN-F019 (Cutbmn!), ard IN-F067A thru D, are also currently isolated witn the MSIVs on receipt of a MSL Radiation liigh - liigh sigml.
'Ibese valves provido a two rinre flcuTath frun the eight MSIV's beforu-r_ eat drains to the min condenser ard are notwilly cpen durirg plant cperation.
'Ihis is essentially the same flcw path as the MSIYa which, upon apprwal of this rocpested cturgo, will not clcso on mL Radiation liigh - liigh.
Sime theso valves do rot involvo any significant difference in fission product Inthway fitzn that of the MS1Vs, deletion of their isolation is consistent with elimimtion of the MSIV isolation fturtion for MSL Radiation liigh - liigh.
All other isolation actuations associated with MSL Radiation function rumin intact urder this requestal chan30.
3 1E2H59J2_S12(IEIC#ftliGNHi_QMillMBTEtt MALYSIS -
'Ihm marnt.igtl.st.1kme crm)LCentatim stathz1_DEMILh13aanWs3Lylih_ilm MshargeLvill rot imolm A.aianificntt itsmaso in_ibcLptT*Allity_pr I
snappens_DLJhtLMildMh_QtE GBly_EMEhntEla me prc$osed amendment does ret irwolve a Ihysical or prucodural charvje to any structure, camponent or system that significantly affects the prtbability or consequencer, of any accident or m1 function of equiptent inportant to safety previously evalustai in the Updated Pim1 Safety Analysis Report (UmAR). We prcposed anerdment will irwolve a change to reactor protecticn ard isolation actuation systems circultz,/ thct will rumve the autautic reactor rhutdown aid main steam line isolation valve (MSIV) closure furetions of the min steam lirn radiation monitor (MSUN).
As demonstrated in Attachnent 3, the methods, procedures ard assunptions used to perform the generic analyses in IRO 31400A aru bourding for the lic$e Croek Generatin) Station with regard to inp1t values.- PSl%G has also prtnidad, in the attachment, reasonable assurance that significantly ircrnased levels of radinactivity in the min steam lines will be controlled expediticusly.to limit both occupational ard emixurnental exposures. Finally,' the MSUN ard offgas radiaticn monitor setpoints are set at 1.5 timos* the nitrogen-16 Lackground dose rate at the monitor locations ard should either or both exceed their alam setpoint, the reactor coolant will te prtmptly sanpled to determine activity-levels and the possible need for additional corrective actions. % ese actions, coupled with the analyses in the 13R, ensure that there will be no significant -
ircrease in the probability or consequences of prwicusly evaluated accidents.
We offgas pre-treatment radiation monitor alam is set at 1.5 times backgrourd or 10 ar/hr. whichever is amatgr. Win 10 mr/hr caveat has been found r-ury to eliminata numerous spurious alarrs (with their attendant distractions of the control room operators) due to current backgrourd 1cvels so Icw (4 to 5 mr/hr) that minor cirt:uit noise or changes in offgas flowrato can initiata an alarm. We 10 ar/hr alam setpoint correspords to.05% of
-the limit of 330 mil 11 curies /second as specified in TS 3.11.2.7.
It is in accortlance with this 'Is that the offgas radiation nonitor alam is set.
Historically, as a point of reference, one leaking fuel pin has produced several thcusand mr/hr levels on the offgas radiation monitor at IKus.
Werefore, the current alam set point of 10 mr/hr prtnidos a conservative
-margin. As background levels ircrease with plant age, the 10 mr/hr alarm will eventually be supplanted by the 1.5 times bac)muund alam setpoint.
L ithtg;gnticm of 1kme crnak Conaratim StatimLQKgi)._in_ngggnknty;gLWith_tle ptggggj charna will not create the rmasibility___of a new or r)Q[etymt_kird of m
aggidgit frta __arw orwiously _ eval _uated.
Other than the circuitry modifications requirtd to accorplish the removal of L
the subject MSUN reactor rhutdown ard MSIV isolation furctions, aralyzcd in l-the UIR, no changes to the physical plant or to the manner in which the plant is cperated are introduced by the requested charge. Werefore, the charrje introduces no possibility for any new or different kird of accident.
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l %e meratim of lkmCrrek Generatim Statim (IKE) 'in accortlar.pn witJLthe
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--wi durrae does rot involve a sign [fjoant ruirtiartin a mmin of_rgfety.
.me amlyses ir, the~ LTR demnstrate that ruoval of the automtic Itactor shut down and min steam line isolation valve (MSIV) closure functions of the min scoam.line radiation ronitor (MSIPM) does not change the corclusions in 'te
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UFSAR that the calculated raalolcgi.:a1 release consequences of the kninding control' rod drtp accident will not examd the acceptable dose limits specified in 10 CFR 100 ard the SRP 'See h Caparison Tables 2a & 2b of Attachment 3).
mis, along with the adiitiorni actions described in Attachmnt 3, ensure tMt there is no significant decrease in any n : gin of safety.
ggotheiam Based upon the above, we have dctatnined that this proposed chango does not involve a Signiricant HazaMs Consideration.
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