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TO PETITION        I FOR ADMISSION AS PARTY, HEARING AND          A .. * * ' " "
TO PETITION        I FOR ADMISSION AS PARTY, HEARING AND          A .. * * ' " "
ENVIRONMENTAL IMPACT STATEMENT          N 4/h i- s By letter dated July 2, 1981, Wisconsin Electric Power Company (" Licensee") filed with the Director of the Office of Nuclear Reactor Regulation ("NRR") Technical Specification Change Request No. 69. In this Request, Licensee seeks to amend Facility Operating Licenses DPR-24 and DPR-27 for the Point Beach Nuclear Plants Units 1 and 2, respectively.            Specif-ically, Nuclear Regulatory Commission (" Commission") c.pproval of these license amendments would permit Licensee to conduct as part of a demonstration program during the fall 1981 refueling outage a verification that degraded or defective steam generator tubes at Point Beach Nuclear Plant Unit 1 can be repaired by inserting Inconel 600 sleeves inside the tubes, thereby bridging l            the degraded or defective portion of the original tubes.              Licensee plans to sleeve several tubes whose degradation exceeds the Point Beach Nuclear Plant Unit l's present Technical Specifica-tion plugging limit.
ENVIRONMENTAL IMPACT STATEMENT          N 4/h i- s By letter dated July 2, 1981, Wisconsin Electric Power Company (" Licensee") filed with the Director of the Office of Nuclear Reactor Regulation ("NRR") Technical Specification Change Request No. 69. In this Request, Licensee seeks to amend Facility Operating Licenses DPR-24 and DPR-27 for the Point Beach Nuclear Plants Units 1 and 2, respectively.            Specif-ically, Nuclear Regulatory Commission (" Commission") c.pproval of these license amendments would permit Licensee to conduct as part of a demonstration program during the fall 1981 refueling outage a verification that degraded or defective steam generator tubes at Point Beach Nuclear Plant Unit 1 can be repaired by inserting Inconel 600 sleeves inside the tubes, thereby bridging l            the degraded or defective portion of the original tubes.              Licensee plans to sleeve several tubes whose degradation exceeds the Point Beach Nuclear Plant Unit l's present Technical Specifica-tion plugging limit.
;
D  ADOC  O    266                                            Y G                PDR                                    $          l Ull
D  ADOC  O    266                                            Y G                PDR                                    $          l Ull


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                                 -.                                                .                    .    .                        ~
                                 -.                                                .                    .    .                        ~
i The Point Beach sleeving demonstration and sleeving programs will utilize a sleeve and joints of the same or similar design as the sleeves and joints that have~ been installed at San Onofre.          See July 2, 1981 letter from Licensee to Harold R.
i The Point Beach sleeving demonstration and sleeving programs will utilize a sleeve and joints of the same or similar design as the sleeves and joints that have~ been installed at San Onofre.          See July 2, 1981 letter from Licensee to Harold R.
Denton, Director, Office of NRR, at 2.                                                      In both repair programs, the sleeves are fabricc* ed from thermally treated Inconel 600
Denton, Director, Office of NRR, at 2.                                                      In both repair programs, the sleeves are fabricc* ed from thermally treated Inconel 600 tubing.          Comparc San Onofre SER Supporting Amendment No. 55, at 4, with July 2, 1981 letter from Licensee to Harold R. Denton, Director, Office of NRR, at 2.                                                    In order to demonstrate that data developed for San Onofre are applicable to the Point Beach steam generators, Licensee will be performing confirmatory testing, including leak rate testing and load carrying capability, with the Point Beach size steam generator tubing.                                                          Id.              Thus, it is likely that the Staff will find no significant hazards considera-tion involved in the Point Beach sleeving demonstration peoject.
;
tubing.          Comparc San Onofre SER Supporting Amendment No. 55, at 4, with July 2, 1981 letter from Licensee to Harold R. Denton, Director, Office of NRR, at 2.                                                    In order to demonstrate that data developed for San Onofre are applicable to the Point Beach steam generators, Licensee will be performing confirmatory testing, including leak rate testing and load carrying capability, with the Point Beach size steam generator tubing.                                                          Id.              Thus, it is likely that the Staff will find no significant hazards considera-tion involved in the Point Beach sleeving demonstration peoject.
l                                  Similarly, while Decade contends that an EIS must be prepared addressing the environmental. impact of Licensee's.
l                                  Similarly, while Decade contends that an EIS must be prepared addressing the environmental. impact of Licensee's.
sleeving program, the Staff found preparation of an EIS' unneces-sary at San Onofre.                        An EIA was prepared by the Staff on the l
sleeving program, the Staff found preparation of an EIS' unneces-sary at San Onofre.                        An EIA was prepared by the Staff on the l

Latest revision as of 11:27, 17 February 2020

Answer Opposing Wi Environ Decade 810720 Petition to Intervene & Request for Hearing.Commission Should Defer Consideration of Petition Pending NRC Review of Util License Amend Application.Certificate of Svc Encl
ML20010B149
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 08/06/1981
From: Charnoff G
SHAW, PITTMAN, POTTS & TROWBRIDGE, WISCONSIN ELECTRIC POWER CO.
To:
NRC COMMISSION (OCM)
References
NUDOCS 8108140137
Download: ML20010B149 (8)


Text

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p 1 August 6, 1981 S \l p AUG10 193; -uI

-l UNITED STATES OF AMERICA C"C' d S s mq ) l BEFORE THE NUCLEAR REGULATORY COMMISSION k '

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/ l WISCONSIN ELECTRIC POWER COMPANY ) Docket Nos. 50-266' N

) and 50-301 (Point Beach Nuclear Plant ) (OL Amendment} CD Units 1 and 2) )

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' JG 1319815 C LICENSEE' S ANSWER OF WISCONSIN'S IN OPPOSITION ENVIRONMENTAL DECADE '

TO PETITION I FOR ADMISSION AS PARTY, HEARING AND A .. * * ' " "

ENVIRONMENTAL IMPACT STATEMENT N 4/h i- s By letter dated July 2, 1981, Wisconsin Electric Power Company (" Licensee") filed with the Director of the Office of Nuclear Reactor Regulation ("NRR") Technical Specification Change Request No. 69. In this Request, Licensee seeks to amend Facility Operating Licenses DPR-24 and DPR-27 for the Point Beach Nuclear Plants Units 1 and 2, respectively. Specif-ically, Nuclear Regulatory Commission (" Commission") c.pproval of these license amendments would permit Licensee to conduct as part of a demonstration program during the fall 1981 refueling outage a verification that degraded or defective steam generator tubes at Point Beach Nuclear Plant Unit 1 can be repaired by inserting Inconel 600 sleeves inside the tubes, thereby bridging l the degraded or defective portion of the original tubes. Licensee plans to sleeve several tubes whose degradation exceeds the Point Beach Nuclear Plant Unit l's present Technical Specifica-tion plugging limit.

D ADOC O 266 Y G PDR $ l Ull

In response to Licensee's July 2 letter, Wisconsin's Environmental Decade, Inc. (" Decade") filed a petition on July 20, 1981. In its petition, Decade requests the Commis-sion to convene an adjudicatory hearing on the proposed licence amendments, and to admit Decade as an intervenor therein.

Decade also asks the Commission to prepare an environmental impact statement ("EIS") on the proposed license emendments.

For the reasons enumerated below, Licensee asks that the Com -

mission defer consideration of the subject petition pending Staff review of Licensee's license amendment application.

Whenever a holder of an operating license desires to amend its license, it must apply for an amendment with the Commission fully describing the changes desired. 10 CFR S 50.90.

If the requested amendment involves a so-called "significant hazards consideration," the Commission will give notice of its -

proposed action by publication in the Federal Register before acting on the amendment. 42 U.S.C. S 2239 (a); 10 CFR SS 50.91, 2.105. No such' prior notice, with opportunity for hearing, is necessary if the amendment does not involve a significant l

hazards consideration. (Of course, the Commission, in its dis-cretion, can dctermine that an opportunity for a public hearing should be afforded. 10 CFR S 2.105 (a) (4) . ) */

l t

  • In support of its request for a hearing and to intervene, Decade inappropriately relies upon Sholly v. NRC, __ F.2d (D.C. Cir. November 19, 1980). While the Sholly deci-sIon ordinarily would be relevant, the mandate of the Court in Sholly was stayed on January.6, 1981, extended on February 12, 1981, and the Commission's petition for certiorari was granted by the Supreme Court on May 26, 1981. The District l (Continued on page 3)

In the present case, Licensee applied for the sleeving license amendments pursuant to 10 CFR S 50.59 in its July 2, 1981 letter. The Commission has not had the opportunity to prepare and issue a safety evaluation in which a formal deter-mination is reached by NRR on whether these amendments involve any significant hazards considerations. Nor has the Commission had the opportunity to consider the environmental impact of sleeving defective or degraded steam generator tubes.at Point Beach. Decade's petition therefore is premature and should be held in abeyance at this juncture pending Staff resolution of these matters and publication in the Federal Register of the Staff's proposed action. Coincident with this determination, Decade's petition should be considered according to the standard enunciated i.. .0 CFR S 2.714, concerning petitions to intervene.__/

The rationale for deferring Decade's petition is partic-

! ularly compelling in view of the Staff's prior consideration l

~

and disposition of these issues in connection with the extensive (Footnote continued from page 2)

I of Columbia Court of Appeals' decision therefore has no present l force or effect. See Federal Rules of Appellate Procedure,

! Rule 41(b) (1980). Furthermore, the applicable criteria for determining whether a-proposed snendment to an operating license involves a significant hazards consideration are those used by the NRC prior to Sholly. See, e.g., Commodity Futures Trading Commission v. British American Commodity Options Corp. , 434 U.S.

1316, 1320 (1977) (" stays entered by the Court of Appeals merely j preserve the regulatory status quo pending final action by this Court").

    • Of course, Decade is free to amend its petition at any time-up to fifteen days prior to the holding of the special prehearing conference, e.g., to set forth with particularity the personal interest of at least one of its members in this proceeding.

, See Houston Lighting and Power Company (Allens Creek Nuclear Generating Station, Unit 1) , ALAB-535, 9 N.R.C. 377, 390 (1979).

l .

m plugging and sleeving program at San Onofre Nuclear Generating Station, Unit 1. On June 8, 1981, NRR issued a Safety Evalua-tion Report ("SER"), Environmental Impact Appraisal ("EIA")

and Negative Declaration on the steam generator repair project conducted by Southern California Edison Corpany at San Onofre.

After evaluating in detail the sleeve repair method proposed by Southern California Edison, the Staff concluded in its SER that it "provides a sound technique for restoring the integrity of degraded or defective steam generator tubing as a primary p ressure boundary, and, thus, provides an acceptable alterna-tive to tube plugging as a repair procedure." Southern Cali-fornia Edison Company (San Onofre Nuclear Generating Station, Unit 1), Docket No. 50-206, Safety Evaluation by the Office of Nuclear Reactor Regulation Supporting Amendment No. 55 to Pro-visional Operating License No. DPR-13, Steam Generator Repair Program and Restart, June 8, 1981, at 13. Moreover, based on its safety evaluation, the Staff further concluded that (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities wi'l be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Id., at 23.

-. . . . ~

i The Point Beach sleeving demonstration and sleeving programs will utilize a sleeve and joints of the same or similar design as the sleeves and joints that have~ been installed at San Onofre. See July 2, 1981 letter from Licensee to Harold R.

Denton, Director, Office of NRR, at 2. In both repair programs, the sleeves are fabricc* ed from thermally treated Inconel 600 tubing. Comparc San Onofre SER Supporting Amendment No. 55, at 4, with July 2, 1981 letter from Licensee to Harold R. Denton, Director, Office of NRR, at 2. In order to demonstrate that data developed for San Onofre are applicable to the Point Beach steam generators, Licensee will be performing confirmatory testing, including leak rate testing and load carrying capability, with the Point Beach size steam generator tubing. Id. Thus, it is likely that the Staff will find no significant hazards considera-tion involved in the Point Beach sleeving demonstration peoject.

l Similarly, while Decade contends that an EIS must be prepared addressing the environmental. impact of Licensee's.

sleeving program, the Staff found preparation of an EIS' unneces-sary at San Onofre. An EIA was prepared by the Staff on the l

l San Onofre steam generator repair program which assessed the environmental impacts of the sleeving project, inclu ing pro-jected cccupational and public radiation exposure levels, j Based on its assessment, the Staff concluded that the San Onofre steam generator repair program would not significantly affect the quality of the human environment. See Southern California Edison Company (San Onofre Nuclear Generating l

i

Station Unit 1), Docket No. 50-206, EIA by the Office of NRR, Supporting Amendment No. 55 to Provisional Operating License No. DPR-13, June 8, 1981, at 5-1. Accordingly, a negative declaration was issued. There is no reason to believe that Licensee's sleeving amendments will result in a contrary en-vironmental finding.

The Staff's review of the San onofre sleeving program is all the more relevant here since Decade raises no factual allegations unique to Licensee. Rather, Decade's concerns are with the sleeving process generally, and its safety and environ-mental consequences. See Decade Petition, at 3-4. Thus, the petition identifies the very issues which the Staff satisfac-torily resolved in its SER and EIA on the San Onofre steam generator repair program, e.g., eddy current test capabilities and, radiation hazards. In summary, all evaluations to date suggest that the Licensee's sleeving program invo'ves no significant hazards considerations and does not require issu-l ance of an EIS.

Finally, while Licensee recognizes the Commission's discretionary authority to convene a hearing prior to acting i

on Licensee's amendment request, no basis exists for the Com-l l

mission's exercising its discretion in this instance. Decade has alleged no rationale for the Commission taking exception to l

l its general rule allowing for NRC resolution of a license amend-ment without a prior hearing if the amendment involves no signi-ficant hazards consideration. On the other hand, the delay which would ensue if a hearing is convened on the rec.aested amendment would result in either deferral of the proposed sleeving program or a sleeving demonstration program without the use of defective tubes. Both results would significantly impede further confirma-tion of the effectiveness of sleeving as a sound and effective alternative to tube plugging.

Licensee therefore recommends that the Commission defer consideration of De'cade's petition until the Staff has c:ompleted its safety and environmental reviews and entertain Decade's request for a hearing at that juncture.

Respectfully submit:ed, SHAW, PITTMAN, POTTS & TROWBRIDGE I ,

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Cerald Charnoff -

Counsel for Licensee 1800 M Street, N.W.

Washington, D.C. 20036 (202) 822-1032 Dated: August 6, 1981

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. August 6, 1981 UNITED STATES OF AMERICA BEFORE THE NUCLEAR REGULATORY COMMISSION WISCONSIN ELECTRIC POWER COMPANY ) Docket Nos. 50-266

) and 50-301 (Point Beach Nuclear Plant ) (OL Amendment)

Un!',s 1 and 2) )

i CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing " Licensee's Answer in Opposition to Petition of Wisconsin's Environmental Decade for Admission as Party, Hearing and Environmental Impact Statement" were served this 6th day of August, 1981 by deposit in the U.S. mail, first class, postage prepaid, upon the following:

Mr. Harold R. Denton Director Nuclear Reactor Regulation Nuclear Regulatory Commission Washington, D.C. 20555 Docketing and Service Section Office of the Secretary U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Kathleen M. Falk, Esq.

Wisconsin's Environmental Decade 302 East Washington Avenue, Suite 203 Madison, Wisconsin 53703 l 1 (. .

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Ge,rald Charnoff e

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