ML20154C217
| ML20154C217 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/04/1988 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20154C219 | List: |
| References | |
| NUDOCS 8805180080 | |
| Download: ML20154C217 (7) | |
Text
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UNITED STATES NUCLEa0 RETLAT0QY COMMISSION VIRF.INTA CLECTQIC AMD POWER COVDANY 00CKET NOS. 50-338 ann 50-339 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDuENTS TO CACILITY ODERATING LICENSES AND OpDORTUNITY Ff)R HEARING l
Tha U.S. Nuclear Reoulatory Commission (the Commission) is considerino 1
issuance of arendments to Facilitv Operatino License Nos. NPF-4 and NPF-7, istuad to the Virqinia Electric and power Company (the licensee), 'or operation e' the North Anna power Station,!! nits Nns 1 & 2 (NA-1&?) located in Louisa County, Virginia.
Tha amendments would revise the NA-1&? Technical Specification (TS) contain-rert air temperature upper limit from 105*F to I?O'F.
NA-l&2 currently operate within an allowable air temperature ranoe of 86'F to 105'F.
The upoer tempera-ture limit is approached during the sumner months because of high ambient and service water temperatures.
This has required implementation of spacialized nanoower-intensive procedures to orevent violation of the NA-1A? TS limits.
This condition exists because there is no practical way to reduce the tempera-ture in a large, enclosed volume or a large body of water in short periods of time. The NA-182 TS action statements specified in Limiting Conditions For Coerations (LCO) 6.15 (Primary Containment Average Air Temperature shall be maintained at equal to or less thar 105'F) and LCO 7.5.1 (Service Water Reservoir and North Anna Reservoir shall be maintained equal to or less than 95'F) provide 8 er 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, raspectively, to restore the respective temperature to within its limit or be in at least Hot Standby in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the 8905180000 08o504 POR ADocg o50003 pp w
i fellowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
For these reasons, the licensee has submitted the proposed change with a Safety Evaluation (SE) to justify increasing the upper containment temperature limit to a value of 120'F.
The containment temperature limit is determined by performing the neces-sary transient analyses to ensure that the containment design criteria are met following a design basis accident.
Temperature is a significant initial con-dition for these analyses. Another important analysis input is the volume of water from the Refueling Water Storage Tank (RWST) available for the quench spray system.
This volume has been defined in such a way as to permit the r.4nimum TS volume to be reduced.
This approach was chosen to permit the use of wide range level instrumentation for TS surveillance.
The plant design basis was reviewed to determine which transients are impacted by the increased service water temperature and containment bulk tem-perature.
The c6ntainment design is based on two Condition IV transients; the Less of Coolant Accident (LOCA) and the Main Steam Line Break (MSLB). As a result of the worst LOCA or worst HSLB, containment integrity is assured if the l
following three ccnditions are satisfied:
(1) the peak calculated containment pressure is less than the pounds per square inch gauge (psig) design pressure of 45 psig, (2) the containment is depressurized to subatmospheric within I hour (3600 seconds) of the accident, and (3) once depressurized, the containment is maintained at a pressure less than atmospheric for the duration of the accident.
)
In support of the proposed change, the LOCA analysis considered a spectrum l
of break sizes and locations.
Several different single-failure scenarios were also censidered. The LOCA analysis actually consists of a peak pressure i
aralysis, a depressurization and a third peak analysis as well as net positive 4
. suctionhead available (NPSHA) analyses for the recirculation spray pumps and the low head safety injection (LHST) pumps.
The initial conditions were determined for each of these analyses to provide the most conservative result.
The peak containment pressure was found to be 44.1 psig.
The length of time to subatmospheric conditions was found to be 3310 seconds.
The MSLB scenarios involved several combinations of break size, break type and power level.
In all, 20 cases were run for the peak te:nperature cases and then repeated for the peak pressure cases.
The peak pressure was found to be 44.9 psig.
The above results indicate that the containment design criteria are not violated at the initial conditions of 120*F containment temperature, 97'F service water temperature and the lower volume of RWST water.
In addition, operability of the electrical and mechanical equipment within the containment at temperatures up to 120*F has also been considered and found to be acceptable provided procedural changes are implemented.
Therefore, the licensee proposes that the appropriate TS can be changed to permit the higher containment air terperature and the lower minimum RWST volume.
Firally, the marirum service water temperature, while analyzed at 97'F would not be changed at this time, since the service water system modifications recently put into place at NA-l&2 can maintain the reservoir ternperature below the currently allowable 95'F.
The proposed TS would increase the required containment test pressure for the integrated (Type A) and local (Types B and C) leak rate tests (NA-182 TS 3.6.1.2) from the current value of 40.6 psig to 44.1 psig. The licensee has reviewed the results of the most recent leak rate tests for NA-l&2 to determine
4 if the tests were conducted at pressures equal to or in excess of that required by the proposed TS discussed above. An evaluation by the licensee has been ce-formed to compare the measured leak rates from the most recent local and in:egrated leak rate tests with the projected leak rates had the tests been ce-formed at the higher pressure required by the proposed TS.
The licensee states that the leak rates which would have been observed had the tests been rue at 44.1 psig would be well within the NA-l&2 TS limit for each type of test.
T'.refore, the licensee proposes that the intent of the proposed NA-l&2 TS for ir:egrated and local leak rate testing have been satisfied by most recent tests.
i However, in order to comply with the proposed NA-l&2 TS, it will be necessary fc-the licensee to perform the subject containment leak rate tests prior to ir::lementation of the proposed TS changes for revising the containment air terperature upper limit from 105'F to 120*F.
Prior to 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 Commission's regulations.
By June 13, 1988
, the licensee may file a request for a hearing with respect to issuance of the amendments to the subject facility operating licenses and any person whose interest may be affected by this proceed-ing and who wishes to participate as a party in the proceeding must file a wr tten request for a hearing and a petition for leave to intervene.
Requests d
for a hearing and petitions for leave to intervene shall be filed in accordance with the Commission's "Rules of Practice for Domestic t.icensing Proceedings" in 10 CFR Part 2.
If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and 1.icensing i
Scard, designated by the Corsnission or by the Chairman of the Atomic Safety and 4
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'. l Licensing Board Panel, will rule on the request and/or petition; and the Se:retary or the designated Atomic Safety snd Licensing Board will issue a netice of hearing or an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and hcw that interest may be affected by the results of the proceeding.
The petition j
should specifically explain the reasons why intervention should be permitted with particular reference to the following factors:
(1) the nature of the petitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the pro-ceeding; and (3) the possible effect of any order which r.ay be entered in the proceeding on the petitioner's interest.
The petition should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene.
Any person who has filed a petition for leave tc intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to fifteen (15) days prior to the first pre-hearing conference scheduled in the proceeding, but such an amended petition rust satisfy the specificity requireeents described above.
Not later than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition te intervene, which must include a list of the contentions that are sought to be litigated in the matter, and the bases for each contention set forth with reason-able specificity. Contentions shall be limited to matters within the scope of the amendments under consideration. A petitioner who fails to file such a supple-nent which satisfies these requirements with respect to at least one contention will not be permitted to participate as a party.
. Those permitted to intervene become parties to the proceeding, subj-et to any limitations in the order granting leave to intervene, and have the opportunity J
to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Comission, U.S. Nuclear Regulatory Comission, Washington, D.C.
20555, Attention: Docketing and Service Branch, or may be delivered to the Comission's Public Document Room,1717 H Street, N.W.
Washington, D.C., by the above date.
Where petitions are filed during the last ten (10) days of the notice period, it is requested that the petitioner promptly so inform the Commission by a toll-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700).
The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to Herbert N. Berkow: petitioner's name and telephone number; date petition was mailed; plant name; and publication date and page number of this FEDERAL REGISTER notice.
A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, and to Michael W. Maupin, Esq., Hunton and Williams, P. O. Box 1535, Richmond, Virginia 23212.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Comnission, the presiding officer or the presiding 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)(i)-(v) and 2.714(d).
. If a request 'or a hearing is received, the Comission's staff may issue the amendments af ter it completes its technical review and prior to the completior of any required hearing if it publishes a further notice for public coment of its proposed finding of no significant hazards considerations in accordance with 10 CFR 50.91 and 50.92.
For further details with respect to this action, see the application for amendments dated March 2, 1988, which is available for public inspection at the Comission's Public Document Room,1717 H Street, N.W., Washington, D. C. 20555.
and at the local Public Document Room Alderman library, Manuscripts Department, University of Virginia, Charlottesville, Virginia 22901.
Dated at Rockville, Maryland, this 4th day of May 1988.
FOR THE NUCLEAR REGULATORY COMMISSION feroertN.Berkow, Director l
Project Directorate Il-2 Division of Reactor Projects 1/II Office of Nuclear Reactor Regulation l