ML20085E786
| ML20085E786 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/08/1991 |
| From: | Olshan L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20085E787 | List: |
| References | |
| NUDOCS 9110210181 | |
| Download: ML20085E786 (9) | |
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UNITED STATES NUCLEAR REGULATORY C0ttilS$10H, COMMONWEALTH EDISON COMPANY DOCKET N05. 50-254 AND S0-2655 NOTICE OF CON 510 ERAT 10N OF, ISSUANCE OF AMENDHENT TO FACILITY OPERATING LICENSE, PROPOSED HO SIGNIFICANT HAZARDS CONSIDERATIONDETERMINATION,ANDOPPORTUNITYFORHEARig The U.S. Nuclear Regulatory Comission (the Comission) is considering issuance of an araendment to Tacility Operating License Nos. OPR-29 and DPR-30 issued to Conronwealth Edison Company (the licensee) for operation of the Quad Cities Nuclear Power Station, Units 1 and 2, located in Rock Island County, Illinois,.
The proposed amendments would r%nge Technical Specification 4.8.H.2.b(2),
which defines a differential temperature criteria for the control room emergency filtrhtion system heater. The proposed change establishes a differential temperature requirement based upon flow, consistent with the design basis of the systen.
Before issuance of the proposed license amendments, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations.
The Comission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Comission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed an.endments would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; 921o210181 o11008 ADOCKOSnog,{g..
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2 or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant redaction in a margin of safety. As required by 10 CFR $0.91(a), the licensee u s provided its analysis of the issue of no significant hazards cons
- ation, which is presented below:
1.
The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The safety objactive of the control room air filtration unit is to provide filtered air to pressurire the control room after a design basis accident to limit control room doses within the limits of GDC.19.
To accomplish this objective, outside air is passed through a rouching filter, heated to assure that relative humidity is below 701,filteredthroughaHEPAfilter/charcoaladsorbercombination and routed to a booster fan and the "B" train of the control room HVAC [ heating, ventilation and air conditioning]. The 70% relative humidity criteria assures that the charcoal adsorbers will function efficiently to limit control room doses.
The proposed amendment provides revised operability criteria for the differential temperature requirement of the CREF [ control room emergency filtration) system heater. This revised criteria is based upon the flow at which the heater operability test is performed.
The proposed Technical Specification does not involve any new operation of the plant or affect any accioent initiators or precursors. The change does not involve the new installation of equipment.
As such, the probability of the accident remains unchanged.
The proposed amendment does not affect the consequences of the accident. The design bases for the heater is to reduce the relative humidity of the atmosphere to the inlet of the charcoal adsorbers to less than 70% to assure efficient charcoal adsorber performance. To achieve a relative humidity of less than 70% assuming that the incomingairsupplyislessthan95'Fwet-bulbtemperature,a 12*F[ delta)Tisrequired. The Technical Specification requirement of15'F[ delta]Tensuresthattherelativehumidityoftheinlet air to the charcoal adsorbers is less than 70% under all flow conditions. This is unnecessarily conservative when the system is successfully tested at flows greater than 1800 cfm. The proposed amendmant revises the differential temperature requirement to establish a [celta]T range of 15'F to 12'F based on a system finw of 1800 cfm to 2200 cfm, respectively. This proposed differential temperature and associate 1 flow requirc nent will ensure that the t - - _ ___
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relative humidity at the charcoal adsorber inlet remains below 70%, provided that the incoming air supply remains below 95*
wet-bulb temperature. As such, the proposed differential temperature requirement will ensure that relative humidity will be maintained at less than 70%. This in turn will ensure efficient charcoal adsorber performance and thus maintain control room doses below the requirements of GDC-19.
2.
The proposed amendment does not create the possibility of a new or different kind of accident from any previously evaluated.
The design objective of the CREF System is to provide filtered outside air to pressurize the control room to limit t.ie control room dose during and after the design basis accident. The control room air filtration unit does not affect any accident precursors or accident initiators. The proposed amendment requests revised differential temperature criteria bases on flow conditions, in order to assure that relative humidity to the inlet of the charcoal adsorbers is maintained below 70%, thereby assuring control room doses are maintained below GOC-19 requirerents. As such, the proposed amendment does not involve any new modes of operation and does not involve the installation of new equipnent.
Conscquently, the proposed amendnent does not create the possibility of a new or different kind of accident from any previously evaluated.
3.
The proposed change does not involve a significant reduction in the margin of safety.
The CREF System is designed to ensure that control room occupants are not subject to excessive radiation doses during an 2ccident.
The limiting dose which can be received by control room occupt.nts is defined in G00-19. The control room dose is dependent on the ef ficiency of the charcoal adsorbers which in turn is dependent upon the relative humidity at the inlet of the charcoal adsorbers.
F:egulatory Guide 1.52, " Design, Ttsting and Maintenance Criteria for Post Accident Engineered-$afety-Feature Atmosphere Cleanup Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants" requires that the relative humidity is maintained at less than 70%.
The existing Technical Specification requires that the heater,
maintain a 15'[ delta]T to assure that the atmosphere at the inlet of the charcoal adsorber is maintained at less than 701 to assure efficient charcoal adsorber performance thereby maintaining control room doses within the limits of GDC-19. The15'[ delta)T is valid for +he range of all temperature / humidity conditions up to an outside air temperature of 95'F wet-bulb temperature.
The proposed amendrcent requests a revised criteria for the differential temperature requirement which will ensure that inlet relative hurr.idity will be limited to less than 70%, based on
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outside air temperature / humidity conditions which correspond to 95* wet-bulb temperature. The requested differential temperature criteria provides a range of [ delta] Ts required for the range of operable flows.
As a result, control room doses will remain below GDC-19 limits.
The margin of safety is not signif1 antly rcouced with this proposed change since control room doses wil's be maintained below G00-19 limits.
The proposed amenduent does not involve a significant relaxation of tie criteria used to establish safety limits, a significant relaxation of the bases for the Limiting Safety System Settings or a significant relaxation of the bases for the Limiting Conditions for Operation.
Therefore, based on the criteria of 10 CFR 50.92(c),thepropose;dchangedoesnotconstituteasignificant hazards consideration.
The HRC staff has reviewed the licensee's analysis and, based on this review,itapoearsthatthethreestandardsof10CFRSC92(c)aresatisfied.
Therefore, tbc NRC staff proposes to determini that the anendnent request involves r.u signtiicant hazards consideration.
The Ccnynission is steking public concents on this proposed determination.
Any connents received within thirty (30) days af ter the date of publication of this notice will be considered in making any final deterrnination.
The Conmission will not normally make a final determination unless it receives a request for a hearing.
Written comments tay be submitted by mail to the Regulatory Publications Branch, Division of Freedom of Information and Publicstions Services, Office of Administration, U.S. Nuclear Regulatory Connission, Washington, DC 10555, and should cite the publication date and page nutber of this FEDERAL REGISTER notice. Written comnents may also be delivered to Room P-223, Phillips Building, 7920 Norfolt Avenue, Bethesda, Maryland, from 7:30 a.m. to 4:15 p.m.
Copies of writt#;r connents received may be examined at the NRC Public Docunent Rooni, the Gelman Building, 2120 L Street, NW., Washington, DC 20555. The filing of requests for hearing and petitions for leave to intervene is discussed below.
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By Lvember 15, 1991, the licensee may file a request for a hearing (ith respect to issuance of the amenduent to the subject facility operating y
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,4 license and any person whose interest inay be affected by this procceding and
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to participate as a party in the proceeding snust file a written
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requec. for a hearing and a petition for leave to intervene. Requests for a
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hearing and a petition for leave tt Htervene shall be filed in accordance with the Camission't. " Rules of Practice for Dcmestic Licensing Proceedings" in i
f4 10 CFR Part 2.
Interested persons should consult a current copy of 10 CFR 2.714
,r-p which is availab?e at the Connission's Public Document Roe % the 021 man Building,
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2120 L Street, NW., Washington, DC 20555 and at the local public docuinent room located at the Dixon Public Library, 221 Henncpin Avenue, Dixtn, Illinois 61021.
'f a quest for a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Commission o; by the Chairman of tne Atomic Safety and Licensing Bnard Panel, will ruit on the request and/c petition; and the Secrete.y or the designated Atomic Gafety and Licensing Board wil. issue a notice of hearing or an eppropriate order.
As required by 10 CFR L714, a petition 'or leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, o
and how that interest may be atfecteo ty th:: re. Its of the proceeding.
The petition shoulo specifically expla'n the reasons why intervention should be permitted with pe.rticular reference to the following factors:
(1) the nature c? the petitioncr's -ight under the Act to te made party to the proceeding; (2) the nat'are en6 exter,t of the petitioner's p"operty, financial, or other interest in ths proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's ina.est. The petition I
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6-si.ould also ider.tify the spc. lc aspect (s) of the subject r.atter of the proceeding as to which petitioner wishes to intervene. Any person who has filed a netition for leave to intervene or who has b=en admitted as a party may amend the petition without requesting leave of the Board up to fif teen (15) days prior to th' first prehearing conference scheduled in the proceeding, but such an annended petition must satisfy the specificity requirements describeu aove.
Not later than fif teen (15) days prior to the first prehearing conference schedu1Ld in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a litt of the contentions which are sought to be litigated in the matter. Each contention nust ::onsist of a specific tatement of the issue of law or fact to be raised or controverted. In addition, the cetitioner shall provide a brief explanation of the bases of the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the pet'tioner intends to rely in proving he cortention at the I w ing. The petitioner must also provide references to those specific sources and documents of which the. -titioner is aware and on which the petitiorer intends to rely to establish those facts or expert opinion. Petitioner must provide suf ficient information to show that a genuine dispute exists with the applicant on a o +.erial issue of law or fact.
Contention:; shall be limited to matters within the scope of the amendment g
under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner who fcils to file such a supplement which satisfies these requirements with respect to at least ona contention will not be permitted to participate as a party.
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Those permitted to intervene beco'ne parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the
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opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and crtss-examine witnesses.
If a hearing is requested, the Comission will make a final determination on the issue of no significant hazards consideration.
The final deterrination will serve to decide when the hearing is held.
If the final determination is that the amendment request Nvolves no significant hazerds consideration, the Comission may issue the amendment and make it imediately effective, notwithstanding the request for a hearing. Any hearing held would take phee after issuance of the amendment, if the final determination is that the amendment request involves a significant hazards consideration, any hearing held woold take place before the issuance of any amendment.
Normally, the Commission will not issu the amendment until the expiration of the 30-day notice period. However, sitould circumstances change during the notice period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the r, omission may issue the license amendment before the expiration of th: 30-day notice period, provided that its final determina..an is that the amendwnt involves no significant hazards consideration. The final determination will consider all public and State comments received. Should the Comission take this action, it will publish in the FEDERAL REGISTER a notice of issuance ar.d provide for opportunity for a hearing after issuance. The Comission expects that the need to take this action will occur very infrequently.
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y; s A request for a hearing or e petition for leave to intervene must te c
filed with the Secretary of the Comission, U.S. Nuclear Regulatory Comission, Washington, DC 20555, Attention: Dc:keting and Services Branch, or may be delivered to the Comission's Public Document Rocc, the Gelman Buf1 ding, 2120 L Streat, MW., Wa,hington, DC 20555, by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is requested thai the petitioner promptly se inforal the Commission by a toll free telephone call to Western Union at 1-(800) 325-6000 (in Missouri 1-(800) 342 6700). The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to Richard J. Barrett: petitioner's name and y
telephone number, date petition was mailed, plant name, and publicatic' date and page-number 'of this FFMRAL REGISTER notice. A copy of the petition-should also be sent to the Office che General Counsel, U.S. Nuclear a
Regulatory Comission, Washington, DC 20555, and to Michael I. Niiler, Esquire; Sidley and Austin, One First National-Plaza, Chicago, Illinois 60699, attorney for the licensee.
Nontimely filings of retitions for leave to intervene, amended petitions,
- supplemental petitions and/or requests for hearint will not be entertained absent a determinatic., by the Commissioh, the presiding officer or the Atomic Safety and Licensing Board that' the petition and/or request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d).
For further details with respect to this action, see the application 2
. for amendment dated September 24, 1991, which is available for public inspection at the Commission's Pu'.lic Document Room, the Gelman Building,
2120 L Street, NW., Washington, DC 20555 and at the local public docunent room located at the Dixon Public Library, 221 Henupin Avenue, Dixon, Illinois 61021.
P +.ed at flockville, Maryland, this 8th day of October 1991, FOR THE NUCLEAR REGULATORY COMMISSION dV 't d' 6 Leonard H. 01shan, Project Manager Project Directorate 111-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation O