ML20084C770
| ML20084C770 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/09/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19280D931 | List: |
| References | |
| NUDOCS 8404300269 | |
| Download: ML20084C770 (4) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMEN 0 MENT NO. 91 TO FACILITY OPERATING LICENSE NO. OPR-50 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENN5YLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1
, DOCKET NO. 50-289
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Pre-Critical Hot Functional Test Program 1.0 Introduction The purpose of this Safety Evaluation is to evaluate the safety of conducting non-nuclear heatup and pre-critical testing of the plant using the repaired steam generators and to make a final detemination as to significant hazards considerations of such pre-critical testing.
On March 23,1981,inCLI81-03,theNuclearRegulatoryCommission(the Commission) authorized the licensee to perfom hot functional testing using non-nuclear heat, subject to appropriate NRC staff review. The staff reviewed the licensee's hot functional test program and approved performance of such testing, which was conducted in August and September of 1981.
Subsequently, the corrosion problem which occurred in late 1981 rendered the steam generators inoperable. Although the authorization to perform hot functinnal testing still exists, theTechnical S any operation (including hot functional testing)pecifications preclude above 250*F with inoperable steam generators. GPU Nuclear submitted Technical Specification Change Request No.125 on May 9,1983, requesting an amendment to approve repairs to defective steam generator tubes using methods other than plugging and requested approval of the use of the repaired steam generators to perform non-nuclear heatup of the plant for pre-critical testing as well as subsequent operation. A Notice of Consideration of Issuance of Amendment and Proposed No Significant Hazards Consideration Determination covering this request appeared in the FEDERAL REGISTER on May 31, 1983. Consnents received on that notice did not address hot functional testing as such, but rather concentrated on the repair process and subsequent nuclear operation with the repaired steam generators.
To facilitate hot testing of the steam generators in order to confirm the adequacy of the repairs, the licensee requested, on July 13, 1983, that their May 9 request be split into two parts:
- 1) pre-critical (non-nuclear) hot functional testing and 2) critical operation.
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. On August 25, 1983, the staff issued its Safety Evaluation (SE) on steam generator repair and return to operation (NUREG-1019), in which it concluded that the repair and test, program is acceptable, that pertinent general design criteria (GDC) have been met, that the steam generator has been returned to its original licensing basis and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the plant with the repaired steam generators.
In partial response to the licensee's July 13 request, the staff also issued, on August 25, 1983, License Amendment No. 86 which permitted the repaired steam generators to be declared operable after repair by the kinetic expansion process for the period of steam generator hot testing. License Amendment No. 86 addressed only the steam generator hot testina based on the staff's understanding of the licensee's July 13 request, but did not permit resumption of the full range of hot functional testing activity. The amendment included a safety evaluation and a final determination of no significant hazards consideration, and its issuance was noticed. As noted in that no significant hazards determination, the Commonwealth of Pennsylvania expressed no concern over this action.
The steam generator hot tests were satisfactorily completed and the plant returned to cold shutdown. A summary of the test results was submitted by the licensee on October 25, 1983, and the staff's evaluation of these results was included in Supplement 1 to NUREG-1019.
The licensee, in its letters dated December 1 and 21, 1983, noted its need for, and requested pennission to proceed with, non-nuclear hot functional testing.
In its letter of February 2, 1984, the licensee summarizes the history of its requests to complete the hot functional test program, points out that its request is encompassed by its original request of May 9, 1983, explains the purpose of the hot functional test program, and again reiterates its request for authorization to perform the remaining pre-critical hot functional test program.
2.0 Evaluation The staff's evaluation of the steam generator repair is covered in NUREG-1019. NUREG-1019 concluded that the repair of the steam generators and the steam generator test program are acceptable and that the steam generators and the Reactor Coolant System (RCS) are within the original licensing basis. Satisfactory completion of the steam generator hot functional test confirmed these conclusions.
As in the case of steam generator hot testing, plant hot functional testing at TMI-1 will involve bringing the reactor system to operating temperatures and pressures utilizina heat from the reactor coolant pumps.
The reactor will not be critical during this testing.
Since the requested operational mode, plant operating conditions, the physical status of the plant, and the potential hazards are the same as for the Steam Generator
Hot Functional Testing (SGHFT) amendment, the safety evaluation considerations and conclusions for the SGHFT Amendment No. 86 also apply to this amendment.
3.0 Conclusions 3.1 Final No Significant Hazards Consideration Determination 3.1.1 State Consultation In accordance with the Commission's regulations, consultation was held with the Commonwealth of Pennsylvania by telephone. The Commonwealth expressed no concern over early pre-critical hot functional testing, either from the standpoint of safety or of no significant hazards consideration determination.
3.1.2 Response to Comments In response to the FEDERAL REGISTER Notice of May 31, 1983 (48 FR 24231) containing the NRC proposed no significant hazards consideration determination, seven sets of comments were received.
Responses only to those comments which address the steam generator repairs and pre-critical testing in relation to a no significant hazards consideration determination were addressed in the SE supporting Amendment No. 86.
The comments and the responses described in Amendment No. 86 are also applicable to this amendment since the plant conditions for pre-critical hot functional testing will be the same as for the plant conditions previously considered for the SGHFT in Amendment 86.
3.1.3 No Significant Hazards Consideration Determination The Commission's regulations in 10 CFR 50.92 state that the Commission may make a final determination that a proposed license amendment involves no significant hazards considerations if 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 accident previously evaluated; or (3)
Involve a significant reduction in a margin of safety.
NUREG-1019 and the information in this SE and in the SE prepared in support of Amendment No. 86 provide the basis for evaluating this license amendment against these criteria. Since the requested operational mode, plant operating conditions, the physical status of'the plant, and dose r,
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consequences of potential accidents are the same as that considered for Amendment No. 86 (Section 3.1.3 of that SE), the staff's evaluation against the above criteria is the same, with minor word changes.
Therefore, the staff concludes that:
(1) Operation of the facility in accordance with the proposed amendment would not significantly increase the probability or consequences of an accident previously evaluated.
(2) Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.
(3) Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.
Accordingly, we conclude that the amendment to Facility Operating License No. OPR-50 permitting non-nuclear pre-critical hot functional testing with the repaired steam generators involves no significant hazards considerations.
3.2 Environmental Consideration We have determined that this amendment does not authorize a change in effluent types or total amounts or an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that this amendment involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
3.3 Conclusion Based on the considerations discussed above, we conclude that non-nuclear pre-critical hot functional testing with the repaired steam generators is acceptable. We further conclude that:
there is reasonable assurance that the health and safety of the public will not be endangered by operation of TMI-1 in accordance with the amended license; such activities will 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.
Dated: April 9, 1984 Contributors: Harley Silver A
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' 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION l
DOCKET NO. 50-289 NOTICE OF ISSUANCE OF AMENOMENT TO FACILITY OPERATING LICENSE AND FINAL NO SIGNIFICANT NAZAR05 CONSIDERATION DETERMINATION (PARTIAL)
The U.S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 91 to Facility Operating License No. OPR-50, issued to 1
Metropolitan Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company, and GPU Nuclear Corporation (the licensees),
which revised the Technical Specifications (TSs) for operation of the Three Mile Island Nuclear Station, Unit No.1 (the facility), located in Dauphin County, Pennsylvania. The amendment is effective as of the date of issuance.
The amendment revises the TSs to permit the steam generators to be declared operable for pre-critical hot functional testing using pump heat (non-nuclear), thereby permitting such testing. As such, it addresses a portion of the Notice of Consideration of Issuance of Amendment and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing identified below.
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. The application for amendment complies with the ::tandards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Notice of Consideration of Issuance of Amendment.and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER on May 31, 1983 (48 FR 24231), and corrected June 14, 1983 (48 FR 27323).
That notice covers a requested amendment which would:
recognize steam generator repair techniques other than plugging, provided such techniques are approved by the Commission; approve the kinetic expansion repair technique; and authorize subsequent operation (both non-r.uclear and nuclear) of the facility with the repaired steam generators.
This notice addresses a portion of, and is encompassed by, that May 31' notice.
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In response to the May 31 notice, requests for hearing were filed by TMIA on May 19, 1983, as amended on June 23, 1983, and by Lee, Molholt, and Aamodt on June 30,1983, as amended on July 13, 1983. Comments were made by six other persons and the Commonwealth of Pennsylvania.
I Under its regulations, the Commission may issue and make an amendment immediately effective, notwithstanding the pendency before it of a request for a hearing from any person, in advance of the holding and completion of any required hearing, where it has detennined that no significant hazards consideration is involved.
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The Comission has applied the standards of 10 CFR 50'.92 and has made a final determination that the amendment involves no significant hazards consideration. The basis for this detemination is contained in the Safety Evaluation related to this action.
Accordingly, as described above, the amendment has been issued and made imediately effective and any hearing in connection with this amendment will be held after issuance.
A final detemination regarding significant hazards considerations on the remainder of the sub[ect matter of the May 31 notice, f.e., nuclear operation with the repaired steam generators, has not yet been made.
The Comission has determined that the issuance of the amenament will not result in any significant environmental impact and that pursuant to 10 CFR $51.5(d)(4) an environmental impact statement or negative declaration at d environmental impact appraisal need Act be prepared in connection with issuance of the amendment.
For further details with respect to the action see (1) the application for amendment dated May 9, 1983, (2) Amendment No. 91 to Facility Operating License No. DPR-50, and (3) the Comission's related Safety Evalation.
All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, N.W., Washington, D.C., and at the Government Publications Section, State Library of Pennsylvania, Education Building, Connonwealth and Walnut Streets, Harrisburg, Pennsylvania 17126.
A copy of items (2)" and (3) may be obtained upon request addressed to the U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, Attention:
Director, Division of Licensing.
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7590-01
, Dated at Bethesda, Maryland this 9th day of April 1984.
FOR THE NUCLEAR REG LATORY COMMISSION
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J m F. Stolz, Chief O erating Reactors Branch #4 Wivision of Licensing
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