ML20127A843
| ML20127A843 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Crane |
| Issue date: | 07/13/1983 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127A737 | List:
|
| References | |
| FOIA-84-794 NUDOCS 8308190157 | |
| Download: ML20127A843 (7) | |
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~t 7590-01 UNITED-STATES NUCEEAR REGULATORY COMMISSION METROPOLITAN-EDISDN COMPANY JERSEY CENTRAL-POWER ANB-EISHT COMPANY PENNSYtYANIA EhEETRIS ESMPANY 6PU NUCEEAR CORPORATION 006KET N0:-50 289 NOTICE-0F CONSIDERATION OF-ISSBANCE-OF-AMENDMENT T0 FA6ILITY 0PERATING-tIEENSE-AND-PROPOSED NO-SIGNIFICANT-HAZARBS 60NSIBERATION BETERMINATION-ANB-SPPORTUNITY FOR-HEARING The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. OPR-50, issued to Metropolitan Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company, and GPU Nuclear Corporation (the licensees),
for operation of the Three Mile Island Nuclear Station, Unit No.1 (the facility) located in Dauphin County, Pennsylvania.
In accordance with the licensees' application for amendment dated January 21, 1983, the amendment would permit increasing by 50 psig, the Reactor Coolant System pressure at or below which the High Pressure Injection (from 1725 psig to 1775 psig), Low Pressure Injection (from 875 psig to 925 psig), and Reactor Building isolation (from 1725 psig to 1775 psig) actuation signals may be bypassed during plant cooldown and depressurization. The setpoints for actuation of these systems during operation and the Reactor Coolant System pressure above which the bypass is automatically removed (when system pressure is increasing) remain unchanged.
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Ene c W 4 s s amended (the Act) and the Comission's regul09fss, NN
P 7590-01
. The Connission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any
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accident previously evaluated; or (3) involve a significant reduction in a margin of. safety.
The proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated since the increase of 50 psi in the level at which the signals may. be bypassed represents only a slight increase in the risk of a loss of coolant event occurring while the signals are bypassed and corresponds only to a slightly earlier time in normal plant cooldown, thus, only slightly higher decay heat generation.
The proposed amendment would not create the possibility of a new or different kind of accident from any previously evaluated since bypassing of these signals upon plant cooldown is presently permitted by the Technical Specifications and is required to prevent undesired actuation of the systems during normal cooldown. The proposed amendment would not involve a change in any margin of safety.
The proposed amendment should further reduce the possibility of spurious system actions since it will provide operating personnel with additional time in which to bypass the automatic initiation signals during normal plant cooldown and depressurization.
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. The Commission is seeking public comments on this' proposed determination.
Any comments received within 30 days after the date of publication of this notice will be considered in making any final detennination. The Commission will not normally make a final determination unless it receives a request for. a hearing.
Comments should be addressed to the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, D.C.
20555, Attn: Docketing and Service Branch.
By August 22, 1983
, the licensees may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written i
petition for leave to intervene. Request for a hearing and petitions for I
leave to intervene shall be filed in accordance with the C' mmission's " Rules o
of Practice for Domestic Licensing 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 Licensing Board, designated by the Commission or by the Chairman of the Atomic Safety and Licensing
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Board Panel, will rule on the request and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by 10 CFR 52.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The
i a-7590-01 petition should specifically explain the reasons why intervention should be l
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 proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest. The petition should also identify the spe:.f fic. 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 to intervene or who has been admitted as a party
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may amend the petition without requesting leave of the Board up to fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than fifteen (15) days prior to tRe first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition b
to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendment under consideration. A petitioner who fails to file such a supplement which satisfies these requirements with respect to I
at least one contention will not be pemitted to participate as a party.
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Those peNnitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
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7590-01.
If a hearing is requested, the Commission will make a final detennination on the issue of no significant hazards consideration. -The final determina-tion will serve to decide when the hearing is held.
If the final determination is that the amendment' request involves no significant hazards consideration, the Commission may issue 'the amendment and make it effective, notwithstanding the request for a hearing. Any
.i hearing. held would take place after issuance of the amendment.
If the final determination is that the amendment involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
Normally, the Commission will not issue the amendment until the expir-ation of the 30-day notice period. However, should 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 Commission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration.
The final determination will consider all public and State comments received. Should the Commission take this action, it will publish a notice of issuance and provide for opportunity for a hearing after issuance. The Commission expects that the need to take this action will occur very infrequently.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission,
1 7590-01 6-Washington, D.C. 20555, Attention: Docketing and Service Branch, or may be delivered to the Commission's public Document Room,1717 H Street, N.W.,
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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 Nurber 3737 and the following message addressed to John F. Stolz:
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 Executive Legal Director, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, and to Shaw, Pittman, Potts, and Trowbridge,1800 M Street, N.W.,
Washington, D.C.
20036, attorney for the licensees.
l 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 Commission, the presiding officer or the Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the petitioner has made a substantial showing of good cause for the granting of a late petition and/or request.
That determination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
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For further details with respect.to this action, see the application for amendment which is available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C., and at the Government Publications Section, State Library of Pennsylvania, Education Building, Commonwealth and Walnut Streets, Harrisburg, Per sylvania 17126.
Dated at Bethesda, Maryland, this l3th day of July 1983.
FOR THE NUCLEAR REGULATORY' COMMISSION
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1]e Jo F. Stolz, Chief -
O rating Reactors Branch #4 ivision of Licensing "ee.
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s 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION ETROPOLITAN EDISON C09ANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COWANY
.GPU NUCLEAR CORPORATION DOCKET NO. 50-289 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO.
FACILITY OPERATING LICENSE AND PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING The U. S. Nuclear _ Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. OPR-50, issued to
. Metropolitan. Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company, and GPU Nuclear Corporation (the licensees),
for operation of the Three Mile Island Nuclear Statiort, Unit No.1 (the
)
facility) located in Dauphin County, Pennsylvania.
In accordance with the licensee'sr,pp ication for ame'ndment dated j
June 20,1983, the proposed amendment would make four revisions to the Technical l
Specifications.
First, it would revise the Technical Specifications to offset a potential non-conservatism in the prediction of peak cladding temperature during a' loss of coolant accident (LOCA). The potential non-conservatism I
i had been previously discovered and reported by the facility vendor. Second,
.it would revise the centerline fuel melt limit in the Technical Specifications for Cycle 5 operation from 19.6 kw/ft to 20.15 kw/ft. The 19.6 kw/ft limit was for Cycle 4 operation and was incorrectly retained for Cycle 5 operation.
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7590-01 Third, the proposed amendment would reduce the reactor protection system flux to pump trip setpoint for two pump operation from 91 percent (%) to 55 percent This reduction is based upon a vendor recommendation
(%) of rated power.
and will provide a common basis for future vendor analyses. Fourth, it would revise the quadrant tilt instrumentation requirements with respect to the The allowable quadrant preferred order of use of the three detector systems.
tilt limits remain unchanged.
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
jh The Commission has made a proposed detemination that the amendment Under the Commission's request involves no significant hazards consideration.
regulations in 10 CFR 50.92, this means that operation o'f the facility in 'accordance with the proposed amendment would not (1) involve a'significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
The Commission proposes, with respect to the first revision discussed above, to detemine that a significant hazards consideration is not involved because the allowable peak LOCA derived linear heat generation rates (LHR) at the 2, 4, and 6 foot core elevations will be reduced in the Technical Speciff-cations for the first 50 effective full power days to compensate for the non-conservatism of the TAFY fuel perfomance code used in the TMI-1 Cycle 5 ECCS i
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analysis.
The TAFY analysis results coupled with the revised LOCA kw/ft limits provide' conservative LOCA predictions relative to the predictions using the as-approved TACO-1 code. _Thus,. this proposed revision would not (1) involve a significant incre$se in the probability or consequences of an accident previously evaluated since i adds conservatism, (2) create the possibility of a new or
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different kind of accident from any previously evaluated since it reduces existing Technical Specification limits, or (3) involve a significant reduction in a margin of safety since it is based on more conservative analyses.
With respect to the second revision of the proposed amendment, the Commission proposes that a significant hazards consideration is not involved since the centerline fuel melt limit being proposed is the same as that cited in the licensees' earlier application for amendment for Cycle 5 operation dated December 28, 1978, which was subsequently reviewed and approved by the Commission.
(See Amendment No. 50 to DPR-50 dated March 16, 1979).
MndmentNo.50 included a determination that a significant hazards consideration is not involved.
- ~ ' Th'us, based on documented analysis, this' proposed revision would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any previously evaluated, or (3) ~ involve a significant reduction in a margin of safety.
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7590-01 With respect to the third revision of the proposed amendment, the Commission proposes that a significant hazards consideration is not involved since the reactor protection system setpoint is being revised so as to introduce additional conservatism. Thus, this proposed revision would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated since it adds conservatism, (2) create the possibility of a new or different kind of accident from any previously evaluated since it reduces existing Technical Specification limits, or (3) involve a significant reduction in a margin of safety since it adds conservatism.
With respect to the fourth revision of the proposed amendment, the Commission proposes that a significant hazards consideration is not involved since the existing quadrant tilt Technical Specification limits remain unchanged. Thus, this proposed revision, since it does not revise existing Technical Specification limits, would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility'of a new or different kind of accident from any previously evaluated, or (3) involve a significant reduction in a margin of safety.
In summary, the Commission proposes to detennine that the amendment (revisions one through four) does not involve a significant hazards consideration for reasons as cited above.
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7590-01 j
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J The Commission is seeking public comments en this p$oposed detemination.
i Any comments received within 30 days after tne date of publication of this notice will be ctnsidered in making any final determination. The Commission will not nomally make a final determination. unless it receives a request for a h' earing.
Comments should be addressed to the Secretary of the Commission, U.S.
Nuclear Regulatory Commission,'-Washington, D.C.
20555, Attn:
Docketing and Service Branch.
x By August 22, 1983 the licensees may file a request for a hearing with respect to issuance of the amendment to the' subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate.M a party in the proceeding must file a written petition for leave to intervene. Request for a' hearing and petitions for leave to intervene shall be filed in accordance with the Commission's " Rules j
of Practice for Domestic Licensing 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 Licensing Board, designated
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by the Commission or by the Chaiman of the Atomic Safety and Licensing Board Panel,,will rule on the request and/or petition and'the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
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7590-01 6
As required by 10 CFR 52.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may he affected by the results of the proceeding. The petition should specificallv 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 proceeding; and (3) the possible effect of any order which may 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 to 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 prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements 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 to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendment under consideration. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will not be permitted to participate as a party.
1
s 7590-01 Those permitted to intervene become parties.to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate _ fully in,the conduct of the hearing, inclu. ding the opportunity to present evidence and cross-examine witnesses.
l If a hearing is requested, the Comm.ission will make a final detemination on the issue of no significant hazards consideration. The final detemina-tion will serve to decide when the hearing is held.
i If the final detemination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment.
If the final determination is that the amendment involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
Nomally, the Commission will not issue the amendment until the expir-ation of the 30-day notice period. However, should 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 Commission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final detemination will consider
t 7590-01
- all public and State comments received.
Should the Commission take this i
action, it will publish a notice of issuance and provide for opportunity i
for a hearing after issuance. The Commission expects that the need to take this' action will occur very infrequently.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Docketing and Service Branch, or may be delivered to the Commission'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
)
d operator should be given Datagram Identification Number 3737 and the following message addressed to John F. Stolz:
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 Executive Legal Director, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, and to G. F. Trowbridge, Shaw, Pittman, Potts, and Trowbridge, 1800 M Street, N.W., Washington, D.C.
20036, attorney for the licensees.
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 Commission, the presiding officer or the Atomic Safety and Licensing Board designated to rule on the petition and/or request,
a.
i-7590-01 9
that the petitioner has made a substantial showing of good cause for the granting of a late petition and/or request..That determination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714( d).
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l For further details with respect to this action, see the ap9 ication for amendment which is available for public inspection,at' the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C., and at the Government Publications Section, State Library of Pennsylvania, Education Building, Canmonwealth and Walnut Streets, Harrisburg, Pennsylvania 17126.
Dated at Bethesda, Maryland, this13th day of July 1983.
FOR THE NUCLEAR REGULATORY COMMISSION 7.
J Rh F. Stolz, Chief 0 erating Reactor.; Branch #4 vision of Licensing
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2 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 NOTICE OF ADDITIONAL OPPORTUNITY FOR COMMENT On May 31,1983, the Commission published in the FEDERAL REGISTER (48 FR 24231) a " Notice of Consideration of Issuance of Amendment to Facility Operating License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing" related to GPU Nuclear Corporation's (GPUN)
May 9,1983 application for amendment-for Facility Operating License No. DPR-50 for the.Three Mile Island Nuclear Station, Unit No. l (the
. facility), located in Dauphin County, Pennsylvania.
The requested amendment would revise the Technical Specifications to recognize steam generator tube repair techniques, other than plugging, provided such techniques are approved by the U. S. Nuclear Regulatory Commission-(theCommission).
l The licensees' application dated May 9,1983, further requested that the Commission approve, within the provisions of the proposed Technical Specification revision, the kinetic expansion steam generator tube repair technique used at the facility, thus permitting subsequent operation of the facility with the as-repaired steam generators.
7590-01 The May 31, 1983 Notice solicited public coments on the Comission's proposed no significant hazards consideration determination and offered
. an opportunity for the licensees to request a hearing and for interested parties to file a written petition for leave to intervene. A number of comments and petitions for leave to intervene were re, eived prior to expiration of the comment period on June 30','~ 1983.
The Comission has recently completed its Safety Evaluation of the requested amendment and has provided i to the licensees and those interested parties that submitted coments and/or filed written petitions for leave to intervene and to the Public D)cument Rooms in Washington, D.C., and Harrishurg, Pennsylvania.
In view of the additional infor-mation contained in the Safety Evaluation, the Comission is reopening the comment period to receive further public. coments on the proposed no significant Hazards consideration puhTished on May 31 at (48 FR 24231).
. Any coments received within 30 days after the date of publication of this notice will tie considered along with those coments previously received in making. a final determination on the amendment authorizing operation of the facility with the as-repaired ~ steam generators after completion of non-nuclear hot functional testing. The Commiission is also publishing a notica of issuance of an amendment authorizing non-nuclear hot
~l functional testing.of tha steam generators. In connection with this amendeent, the Cometssion has made a final determination that sucit l
amendment involves no signtficant, hazards. considerations.
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7590-01 Comments should be addressed to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Wasnington, D.C.
20555, Att:
Docketing and Service Branch.
For further details wf n respect to this action see (1) tb applica-tion for amendment dated May 9, 1983, (2) tne May 31, 1983 FEDERAL REGISTER Notice (48 FR 24231), and (3) the Commission's Safety Evaluation provided in a letter dated : August 25, 1903 (J. Stolz '(f!RC) to H. Hukill (GPUN)).
These documents are available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C.,
and at the Government Publications Section, State Library of Pennsylvania, Education Building, Commonwealth and Walnut Streets, Harrisbu,rg, Pennsyl-vania 17126.
A copy of the Safety Evaluation may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:
Director, Division of Licensing.
Dated at B.ethesda, Maryland, this 25th day of August 1983.
FOR THE NUCLEAR REGULATORY C0!1tiISSI0ft m
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i J in F. Stolz, Chief j erating Reactors Branch #4 ivision of Licensing 1
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