AECM-89-0223, Application for Amend to License NPF-29,revising Operating License Condition 2.C(36) to Extend Implementation Date for Neutron Flux Monitoring Until Fifth Refueling Outage

Application for Amend to License NPF-29,revising Operating License Condition 2.C(36) to Extend Implementation Date for Neutron Flux Monitoring Until Fifth Refueling Outage

ML20011D546
Person / Time
Site:	Grand Gulf
Issue date:	12/20/1989
From:	Cottle W SYSTEM ENERGY RESOURCES, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20011D547	List: AECM-89-0223, Application for Amend to License NPF-29,revising Operating License Condition 2.C(36) to Extend Implementation Date for Neutron Flux Monitoring Until Fifth Refueling Outage ML20011D548
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 AECM-89-0223, AECM-89-223, NUDOCS 8912270383
Download: ML20011D546 (8)

Text

{{#Wiki_filter:. (e. E $ ystem ' c: S gggy h$ Port G bson. MS 39150 Tel 601437 6809 William T, Cottle December 20, 1989

• e Pmstamt NucJear Opermions U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C.

20555 Attention: Document Control Desk Gentlemen:

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Modification of Reg. Guide 1.97 Compliance Schedule for Neutron Monitoring; Proposed Amendment to i the Operating License Condition 2.C(36) AECM-89/0223

REFERENCES:

) 1) GE NEDO 31558 dated April 1, 1988; "BWR Owners Group Topical Report Position on NRC R.G. 1.97 Rev. 3 Requirements for Post-Accident Neutron Monitoring System" 2) AECM-88/0083 dated April 28, 1988; GGNS Plant Specific Design Evaluation for NEDO 31558 3) AECM-88/0110 dated July 1, 1988; Modification Reg. Guide 1.97 Compliance Schedule for Neutron Monitoring; Proposed Amendment to 0.L. Condition 2.C(36) 4) AECM-89/0013 dited February 6, 19R9; RG 1.97 Neutron Monitoring System;- Request for Commitment Modification 5) NRC letter dated July 21, 1989 (MAEC-89/0228) regarding Post Accident Neutron Flux Monitoring 6) AECM-89/0204 dated-December 5, 1989 regarding the Quarterly Status Report for RG 1.97 Neutron Monitoring System. l System Energy Resources, Inc. (SERI) is submitting by this letter a proposed change'to Attachment 1 to Grand Gulf Nuclear Station (GGNS) Operating j License Condition 2.C(36). The proposed change requests an extension to the implementation date for neutron flux monitoring until-the fifth GGNS refueling outage. This request is based on the ongoing review.by the NRC of the BWROG j Topical Report (NEDO 31558) regarding alternate Regulatory Guide (RG) 1.97 Neutron Monitoring Requirements (Reference 1) and the GGNS plant specific evaluation report on conformance to the NEDO-31558 alternate requirements (Reference 2). Od 1 A9120601/SNLICFLR - 1 I 8912270383 891220 I

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v ,. ;3 e AECM-89/0223 '- a Prg3 2 g, ~ As' discussed in the, enclosed Operating License Change Request (OLCR). i NL-89-02,.SERI has} simultaneously pursued an(evaluation of=(1),the post accident safety function for neutron monitorinC through the GE BWR Owners Group and (2)'thesinstallation of an excore neutron monitoring system by the fourth GGNS refueling outage as committed by SERI in Reference 4.- The excore : neutron moni.toring system approach was approved by the NRC in Reference 5. However, based on findings presented in NEDO 31558, SERI believes that-the intent of RG 1.97 can be met by-existing BWR neutron monitoring a instrumentation. Therefore, resolution by NRC on this issue through the BWROG ~ 'I is considered necessary to establish ancoverall-BWR= industry position for RG 1.97 and to avoid any unnecessary expenditur'es and diversion of manpower resources on the~part'of SERI.

As noted in:the.GGNS Neutron' Monitoring System' Quarterly Report

-(Reference 6), SERI'will need to place an order for the proposed excore' system- ~ .by mid February 1990 to-meet a fourth ~ refueling outage installation schedule. To allow time for SERI review of the NRC Safety Evaluation Report (SER), an y issue date of-early January 1990 would-be. required for:the.SER. This schedule-j was discussed with Mr. L. L. Kintner (NRC Project Manager)-on Nosamber:8, 1989. At that time it was agreed;that an application for extension to GGNS l Operating License Condition 2.C(36)'shouldfbe requested for neutron monitoring. ~ j s Therefore, based on the limited time for further resolution of this issue,' SERI requests that an. extension _be granted to GGNS Operating License-Condition 2.C(36) until=the fifth GGNS: refueling outage-for implementation'of 9 a neutron monitoring system to comply with RG 1.97. 'Your approval of this application for-amendment is requested by February 9,.1990, i In accordance with the provisions of'10CFR50.4 the original of the' requested amendment is attached'and the appropriate copies will3be distributed. The' attached OLCR-NL-89-02 provides the' technical justification and discussion to support the requested amendment. This' request for amendment has been reviewed and accepted by the GGNS plant Safety Review Committee and. the Safety Review Committee. Based on'the guidelines present in 10CFR50.92, SERI has concluded that j this proposed amendment involves no significant hazards. H Yours truly, i 4:.4.D 's [9 u WTC:tkm

Enclosure:

Affirmation per 10CFR50.30 ,l

Attachment:

OLCR-NL-89-02 4 1 cc: (See Next Page)

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'I t = .t 1 DEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION L 1, ~ 1 ~ - (. / t' g t u 71 e g LICENSIE'NO: NPF-29 ^\\ ~ -e.- ,4,i, r ) + i. s t y. . DOCKET No. 50-416 l j g ' - + y IN THE MATTER OF i MISSISSIPPI POWER &' LIGHT COMPANY and> SYSTEM ENERGY RESOURCES, INC. and. SOUTH MISSISSIPPI ELECTRIC POWER; ASSOCIATION . AFFIRMATION I, W. T. Cottle,-being duly sworn,catate that I am Vice President, Nuclear Operations-of System Energy Resources, Inc.; that on behalf of System Energy Resources, Inc., and South Mississippi' Electric Power Association I am authorized by System Energy Resources,-'Inc.-to sign-and-file with the Nuclear. Regulatory Commission, this application for amendment of~the Operating License; of the Grand Gulf Nuclear: Station; that:I' signed this; application as Vice s President,' Nuclear: Operations;of System Energy Resources,. Inc. ; and that the statements made.and the matters set forth'therein are true and' correct to the best of my knowledge, information and belief. wp CL___ W. T. Cottle-9 STATE OF MISSISSIPPI, COUNTY OF CLAIBORNE~ SUBSCRIBED:ANDSWORNTObeforeme,aNotary$hblic,fnandforthe. County and -State abovei named,1 this ' 4 T/' day:of / > # cM /XA, , 1989. (SEAL) hMR 2: &Aric / ?g Not'd'ry Public My commission expires: 'b ' 5 .A9120601/SNLICFLR - 5' Y +

) s i Attcchrt:nt. to AECM-89/0223 - ,c y ;. OLCR - NL-89-02 -Extension of post-Accident Neutron Flux Monitoring Upgrade Implementation Schedule = I. SUBJECT Facility Operating' License No. NPF-29; Operating License Condition 2.C(36) - Emergency Response Facilities; Attachment 1, Item (c)(4). II. > DISCUSSION-The proposed change extends the implementation date for installing:or upgrading the neutron flux monitoring system until prior'to startup; 'following the fifth refueling outage. The current license condition 1 ispehifies th'at the RegulatoryiGuide'(RG) 1[.97requirementsfor'the. ~ ' " neutron: flux monitoring system be impleinented prior to startup following, th'_fourt'h refueling outage'(Refer to Attachment'l to NPF-29). e AscommittedinlAECM-89/0013 dated @eSruary 6,1989, SERI is in the ' process of~ implementing an excore neutron' monitoring system to comply. with GGNS, Operating Lic,ense Condition 2.C(36)'by the fourth'GGNS _ s refueling outage (RF04)l.:The status;oflodr, actions to implement this. ' system was discussed in a recent neutron monitoring system quarterly: status. report (AECM-89/0204 dated December 5, 1989). As noted-in this report, SERI's current plansLare to issue the contract for,an excore. neutron. monitoring system in'mid February.1990? However, SERI recognizes.that review of the BWR Owners Group (BWROG) Topical Report-(NEDO 31558) as provided to the NRC on April 1, 1988 is~ ~ still under review by.the NRC. SERI believes that NEDO 31558 is technically-sound and provides' reasonable alternatives to RG 1,97 . requirements and justifies-utilization of the existing IRM/LPRM: system for GGNS. Even though SERI.is in the process of implementing;a neutron. monitoring system (NMS) to comply with Operating License Condition 2.C(36), further, efforts by SERI on this project could result ~ p in. undue 1 diversion of resources and potentially. unnecessary costs'until' final NRC position on the topical r'eport isJcomplete' SERI believes it-I prudent to await issuance of the NRC Staff's Safety Evaluation _ Report j '. (SER)'on the topical report prior,to continuing;further effort on l installation of a RG 1.97 neutron monitoring system.,:In addition, SERI submitted a plant specific design. evaluation detailing'conformance to. NEDO'31558-on. April 28, 1988!(AECM-88/0083)._"Similarly, NRC response to the GGNS plant specific submittal has not-been received. l l' In order'to allow time for SERI' evaluation'of the NRC resolution of.this l_ issue prior to issuance of a February 1990-neutron' monitoring system L purchase order, SERI would need to receive' the'SER 'in early; January 1990. l-Therefore, SERI. requests ~that the GGNS. Operating License Condition i 2.C(36) Attachment 1 be amended to require-implementation of a RG 1.97 neutron monitoring system prior to startup following.the fifth refueling . outage. A9120601/SNLICFLR - 6

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]j .y [AY.tachment to AECM'89/0223: i" ' ~ .\\ r 4 g _' ? Et i -III. JUSTIFICATION. .m. 'deceptkb'ility'of'xistingNMSDesign4perNEDO31558andGGNSplant~ E ~ A. .-Specific Design Evaluation.

NEDO 31558 provides the BWROG's' evaluation of the post-accident neutron monitoring system as applied to boiling water reactors for

,the purposes of' establishing post accident system requirements. The 1 results of the evaluation performed-in;NEDO_31558 for the analyzed events:and the associated operator' actions conclude that thez specified requirements of RG 1.97 should-be-reduced. SERI-has bN an active member ofi the RG:1.97 BWR Owners Group $ Subcommittee which was established;to' evaluate the Regulatory Guide) 1.97 requirements based on a review of the' neutron monitoring ' system's-post' accident safety functions. While SERI comitted to instali anfexcore neutron monitoring system at the fourth refueling-out' age for meeting RG.1.97, we believe that NRC review of:the,BWR. OwnersGroupTopicalReportshould'.befcompletedprior;toi -implementing this system'..NRC review!is requested in order (1) to preventanyunnecessarymonetaryexpenditures[and~ resource ( _ commitments, (2).to establish appropriate BWR post accident designs basis for the post accident neutron monitoring system,['andl(3) to ~ establish appropriate' design requirements for-RG=1.97' ori neutron. monitoring.: In addition, SERI submitted a plan specific' design evaluation.for the GGNS' neutron monitoring system'as it pertains to the alternat'e i requirements presented in NEDO 31558,(Reference 2)'in April 11988; To date NRC review of the GGNS specific evaluation is also,, outstanding. 1 JSince the present GGNS design meets:the criteria'provided in BWROGL License' Topical Report (NEDO-31558,' as supported:by the plant-specific evaluation, extension of the implementation'date:for a NMS meeting RG 1.97 guidance is~ justified..This proposedl extension allows the'NRC to complete'their evaluation of;the BWROG , topical report for establishing' appropriate design: requirements. B. GGNS Efforts to Resolve' Concern for OL Condit' ion 2.C(36) As discussed'in the recent HeutroniMon'itoring= System'Quakterly' Status Report dated December 5,,1989,.SERI-has actively pursued the ainstallation of'an excore neutron < monitoring system to satisfy. Operating' License Condition'2.C(36)J

Attachment:

1. This included-

preparing'the initial excore neutron monitoring system' design criteria, environmental design criteria,-penetration design specifications and(overall system purchase specification'. The GGNS q

design is similar tofthattinstalled by pennsylvania power and-Lights ,for RG;1.97.on SusquehannaLSteam Electric Station. Detector sensitivity;and monitoring range is also expected to be comparable-to that obtained'by Susquehanna (10E-4 to710E-5% power). = f A9120601/SNLICFLR '7 1

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Attcchment'to:AECH-89/0223 s

4 y.. + .t 'I Continuation of SERI efforts to' meet'an,RF04Lschedule'(Oct 1990)' will require =the issuance;of a purchase specification-in mid-February.1990. In" lieu of.NRC extension toLthe. Operating License s Condition lby-February'9, 1989, SERI"willlhave to continue -implementation on the schedule provided in'the: referenced quarterly status report. j 3, ' i Therefore, SERI has worke'd in good faith to resolve this lssue: dealing with. post accident-neutron, flux monitoring. IV. SIGNIFICANT HAZARDS CONSIDERAYIO'NS The proposed amendment would modify'GGNS2Operding LicenseL RG 1.97 required:neutrori' monitoring l system for{antadditional' outage [j Condition 2.C(36) Attachment 1.to extend;thelimplementation date:of the; (i.e., the fifth refueling. outage)'. This. extension;is requested _-based on' the' ongoing review by.the NRC of the GE BWR Owners Group. Topical Report. 31558 regarding alternate RG.1.97. requirements for post-accident neutronE monitoring. This would allow" additional (time'necessary for the NRC.to; 7 establish the specific system requirements for: RG 1.97 on'BWR's. 4 ?- In accordance with~the requirements'of 50CFR50.92,htheTfollowing' ~,.' 4 -discussion is'provided'in support' of the determinatiorc that' no 'significant' hazards are created or1 increased by'the' changes proposed;in this amendment requestl 1. $No significant increase,in the probabilit or[theLconsequencesofan ? accident previously evaluated results from this proposed change 't 'because: 7 s' The absence of a post' accident neutron monitoring. system during~.n ~ a. n the.fifth: fuel' cycle does notiinvoliteLa.significantnincrease,in-theprobabilityof-hnaccident'previouslylevaluatedsincejthe1 ~ ~ l-absence of the proposed system' modification would not affect 7 3 reactor operation. The post' accident" neutron flux monitoring: system provides post-accident indication'oftreactor power and;

• does not provide 'any signals to. actuate' engineered safety.

j features or.to trip the react'or'.s. Furthermore, reactor. trip' A signals from the present ~ neutron flux' monitoring. system to 'the l reactor protection-system-will not be changed'as a result'ofJ U the installation.of a post accident neutron monitoring system. s J w. .n L b. The consequences of an accident previously:' analyzed' hive been> evaluated.for significant. increase'as a result"of:the'proposedi L, delay in installation of the post accident neutron: flux: 4 monitoring' system. If the new(system.were' installed ~during the? J fourth refueling' outage, fit would provide limited post: accident 34 monitoring improvements over the presently installedusystem. ' However, the presently installed system 31s expected:to~ function .l during the initial phase of an accident <(including a LOCA) to'~ j indicate subcritical reactor power.9tLong termjmonitoring is available-through the APRM-channels-where operator action is q 'au e <A9120601/SNLICFLR - 8 0 r o 6 4s e > ) 4

i .Atttchment to AECM-89/0223 required at the APRM downscale alarm.- In addition,~.other measures and indications can provide the operator.with reactor power information as discussed below:- A 1. The present control. rod position indication system 4 .provides the reactor operator with-information that all rods are inserted. ii. Qualified instrumentation such as reactor. pressure, l suppression pool temperature and safety relief valve (SRV) actuation' provide.the reactor operator with post-accident-information for assessment of reactor power. I 111. The' Emergency Procedures'(Eps) are symptom based and-provide appropriate conservative actions if reactor power can not be directlyLmeasured in a post-accident situation. The EPs contain action" steps which mitigate the-symptomatic effects of design basis events (such as LOCA) and beyond. design basis events:(such as'ATWS). Therefore, the consequences of:an accident previously evaluated:will not be significantly increased bycthe absence of a post accident neutron flux monitoring system during the fifth fuel

• cycle.

2.] 1This proposed change will not.crea'tei the possibility ~of a-new or 'different, kind of accident than-any'previously evaluated because: t The neutron monitoring. system required by RG 1.97 will provide ,, addit'ional, post' accident, monitoring capability by performing a. ' mitigative role during an' accident. Its installation will~ noti preclude or, prevent any-accident. Asf such,: delaying the . installation ofcthe>RG 1.97. post accident; neutron monitoring' system will,not: create the possibility'of=a-new'or different kind of-accident. During the extension period, the present' neutron monitoring system will remain unchanged: from the configuration that 'was.previously~ evaluated in the;FSAR. Che' current:GGNS: neutron' monitoring' system-has:been evaluated using alternate criteria proposed in NEDO-31558 and would'be considered acceptable for continued operation. Therefore, delaying' installation of the - RG ;L.97 post accident neutron monitoring system will'not create the possibility-of alnew or different kind of accident ^fromfany previously evaluated; 3. This proposed change does not-involve:a sig'nificant reduction in the margin of safety because: -Design,. function, and operation, of the existing GGNS neutron f ' monitoring system will remain the same., Additionally, no additional reactor protection. trip functions will be performed by'the RG 1.97 posti. accident monitoring system instrumentation..Ep actions are conservative with respect to the use of the NMS for verification that the-reactor is shutdown. If'not available'during an accident scenario,(operator actions are specified which will lead to= safe reactor shutdown. Because these actions lead to a safe plant condition (reactor shutdown), the margin of safety is not 'significantly reduced'. A9120601/SNLICFLR -19' j f n -}}