ML17258A876
| ML17258A876 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 03/02/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17258A874 | List: |
| References | |
| NUDOCS 8103180276 | |
| Download: ML17258A876 (16) | |
Text
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-244 ROCHESTER GAS AND ELECTRIC CORPORATION NOTICE OF ISSUANCE OF AMENDMENT TO PROVISIONAL OPERATING LICENSE The U.S. Nuclear Regulatory Conmission (the Coamission) has issued Amendment No.
36 to Provisional Operating License No.
DPR-18, to Rochester Gas and Electric Corporation (the licensee),
which revised the Technical'pecifications for operation of the R.E. Ginna Plant'facility) located in Wayne County, New York.
This amendment is effective as of its date of issuance.
The amendment incorporates technical specifications regarding minimum water level above the reactor vessel flange during refueling operations.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
The Commission has made appro-priate 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.
Prior public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.
The Coranission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal neednot be prepared in connection with issuance of this amendment.
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7590-01 For further details with respect to this action, see (1) the application for amendment notarized November 12, 1980 (transmitted by letter dated November 17, 1980), (2) Amendment No.
36 to License No.
DPR-18, and (3) the Commission's related Safety Evaluation.
All of these items are available for public inspection at the Commission's Public Document
- Room, 1717 H Street, N.W., Washington, D.C. and at the Rochester Public Library, 115 South Avenue, Rochester, New York 14627.
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.
Dated at Bethesda, Maryland, this second day of March, 1981.
FOR THE NUCLEAR REGULATORY COMMISSION Dennis M. Crutchfield, ief Operating Reactors Branch 85 Division of Licensing
I'ID 8Di U.S. NUCLEAR REGULATORY COM
'ION REACTOR FACILITYFEE DETERMINATION 1
FEE FORM TYPEIOtecadnxc PRELIMINARY FINAL AMENDEO INSTRUCTIONS. Fill in itemS 1 thrbugh 14, aa apphcable, and send the Original copy to the License Fee Management Branch,
- 2. DDGKET NUMBER(Si 4
LICENSEE SII YZdMl' PLANT NAME ANDUNITISI 6
DAT OF APPLI ATIO lf'~ d'4' FEE REMITTED YES NO
- 8. LICENSEE FEE DETERMINATION CLASS'ii CLASSi CLASSX CLASSie CLASSiv CLASSVi TXSMPZ 9
SUBJECT
~rvd' lo, TAC NUMBER ASSIGNEDlllavarlablel
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11 APPROVAL
'.trrn onogn AMrrroutrrrrruMsrnrsr DATE OF 12 NRC FEE DETERMINATION The above application has been reviewed in accordance with Section 17022 of Part 170 and is properly categorized.
The above apphcation has been renewed in accordance with Section 170 22 ol Part 170 and is incorrectly classihed.
Fee should be classtesl:
JUSTIFICATION FOR CLASSIFICATIONOR RECLASSIFICATION This application is a Class type of action and is exempt from fees because ilis:
Filed by a nonprofit educational institution.
Filed by a Government agency and is nol tor a power reactor.
For a Ciass I. II. or III amendment which results from an NRC request dated for the application and the amendmenTesto sdnpltfy or clarity License or Technical Sliecificalions: has only minor safely significance: and Is being issued for the convenience of NRC (muszaceetafz of the criterial.
Other fStale reason there/on REIBi n nieli DATE 14 F I S
L cERTIF IGATIDN The prehminaty iee deterrninationnas been reassessed and is hereby atfirmed ATURErrrrorecraranaperdrBr nCnC
!ri DATE FOR LIC SE FEE MANAGEMENTBRANGH USE ONLYfAIIothers do nor write below this iinel Tne above exemption iebuesl has been reviewed and is hereby accepted as being exempt siGNATURErcniel zFarBr DATE PeCOrdx Servieea BranCh DL Branch Chief DISTRIBUTIONBY LFMB LFMBExemption Foe LFMBReactor Fee
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Docket No. 50-244 FEB 10 1981 Hr. John E. Maier Vice President - Electric 8 Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Hr. Maier:
F'Eg 18 1981' g~ gggAATCC%
gggNI5508 The Commission has issued the enclosed Amendment ~No.
~ 5 to Provisional Operating License No. DPR-18 for the R.E. Ginna Nuclear Power Plant, Unit No. l.
The amendment consists of changes to the Technical Specifications in response to your application notarized October 30, 1980 (submitted by letter dated November 4, 1980).
As discussed in a telephone conversation with your staff on December 23.
1980, reference to the Shift Technical Advisor has been deleted from the October 30, 1980 request.
lie mutually agreed upon this change.
The addition of the Shift Technical Advisors (STAs) to the or ganiza-tional chart resulted from your request notarized April 9, 1980 (submitted by letter dated April ll, 1980).
This request was subsequently superseded in part by your application and letter of October 30, 1980 and November 4, 1980, respectively, and in part by another request notarized November 5, 1980 (submitted by letter dated November 13, 1980).
This la,tter request deals with Three Mile Island Lessons Learned implementation items and includes changes to the organizational technical specifications related to the inclu-sion of the STAs.
Although supersession of the April 9/April 11, 1980 submittal would ostensibly delete necessary changes to Figure 6.2-1 of the Ginna Technical Specifications to include the STA in the orga-nization chart, we will review this addition as part of the November 5/
November 13, 1980 submittal.
Please inform us if"you are not satisfied with this approach or if further changes are necessary.
The letter of October 30/November 4, 1980, upon which this amendment is based, revised certain provisions in Section 6 of Ginna Technical Specifications Appendix A to reflect changes in the corporate organizational structure.
Specifically, the RE. Ginna Nuclear Power Plant management organization chart (Figure 6.2-1) has been revised to reflect recent changes in the RG&E offsite organization.
Two new positions of Senior Vice President have been created, Senior Vice President - General Services and Senior Vice President-
~pigance and Rates;-
Reporting to the former is the General Manager-Purchasing and Public Affairs.
Reporting to the latter is the Vice
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FEB 10 1S81 President - Rates.
The previous position of Chief Engineer has been changed to 'Vice President and Chief Engineer, reporting to the Executive Vice President who in turn reports to the President of Rochester Gas and Electric Corporation.
Me have reviewed the above proposed changes to the Technical Specifi-cations, reflecting the recent revisions of the management organization
- chart, and find these changes acceptable because they do not diminish the level of safety with respect to organization and technical resources provided by the existing Technical Specifications.
The organizational changes also meet the provisions of 18.7-1976/
ANS-3.2 as endorsed by Regulatory Guide 1.33 and are, therefore, acceptable.
The amendment applies to the organizational structure and therefore, does not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the 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 negati-ve declaration and environmental impact appraisal need not be prepared in connection with the issuance of the amendment.
Since the amendment applies to the organizational structure, it does not involve significant new safety information of a type not considered by a previous Commission safety review of the facility. It does not involve a significant increase in the probability or consequences of an accident, does not 'involve a significant decrease in a safety margin, and, therefore, does not involve a significant hazards consideration.
1<e have also concluded that there is reasonable assurance that the health and safety of the public wil 1 not be endangered by this action and that the issuance of this amendment will not be inimical to the cordon defense and security or to the health and safety of the public.
A copy of the Notice of Issuance is also enclosed.
Sincerely Enclosures and cc:
See next page Dennis M. Crutchfield, Chief Operating Reactors Branch 85 Division of Licensing
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Amendment No. g 5 to License No.
DPR-18 2.
Notice of Issuance cc w/enclosures:
See page 4
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Docket No. 50-244 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 10, 1981 Mr. John E. Maier Vice President - Electric 8 Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Mr. Maier:
The Comission has issued the enclosed Amendment No. 35 to Provisional Operating License No.
DPR-18 for the R.E.
Ginna Nuclear Power Plant, Unit No. 1.
The amendment consists of changes to the Technical Specifications in response to your application notarized October 30, 1980 (submitted by letter dated November 4, 1980).
As discussed in a telephone conversation with your staff on December 23, 1980, reference to the Shift Technical Advisor has been deleted from the October 30, 1980 request.
We mutually agreed upon this change.
The addition of the Shift Technical Advisors (STAs) to the organiza-tional chart resulted from your request notarized April 9, 1980 (submitted by letter dated April ll, 1980).
This request was subsequently superseded in part by your application and letter of October 30, 1980 and November 4, 1980, respectively, and in part by another request notarized November 5, 1980 (submitted by letter dated November 13, 1980).
This latter request deals with Three Mile Island Lessons Learned implementation items and includes changes to the organizational technical specifications related to the inclu-sion of the STAs.
Although supersession of the April 9/April 11, 1980 submittal would ostensibly delete necessary changes to Figure 6.2-1 of the Ginna Technical Specifications to include the STA in the orga-nization char t, we will review this addition as part of the November 5/
November 13, 1980 submittal.
Please inform us if you are not satisfied with this approach or if further changes are necessary.
The letter of October 30/November 4, 1980, upon which this amendment is based, revised certain provisions in Section 6 of Ginna Technical Specifications Appendix A to reflect'hanges in the corporate organizational structure.
Specifically, the R.E.
Ginna Nuclear Power Plant management organization chart (Figure 6.2-1) has been revised to reflect recent changes in the RGSE offsite organization.
Two new positions of Senior Vice President have been created, Senior Vice President - General Services and Senior Vice President-Finance and Rates.
Reporting to the former is the GeneraI Manager-Pur chasing and Public Affairs.
Reporting to the latter is the Vice February 10, 1981 President - Rates.
The previous position of Chief Engineer has been changed to Vice President and Chief Engineer, reporting to the Executive Vice President who in turn reports to the President of Rochester Gas and Electric Corporation.
We have reviewed the above proposed changes to the Technical Specifi-cations, reflecting the recent revisions of the management organization
- chart, and find these changes acceptable because they do not diminish the level of safety with respect to organization and technical resources provided by the existing Technical Specifications.
The organizational changes also meet the provisions of 18.7-1976/
ANS-3.2 as endorsed by Regulatory Guide 1.33 and are, therefore, acceptable.
The amendment applies to the organizational structure and therefore, does not authorize a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the 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 riot be prepared in connection with the issuance of the amendment..
Since the amendment applies to 'the organizational structure, iC.does not involve significant new safety information of a type not considered by a previous Commission safety review of the facility. It does not involve a significant increase in the probability or consequences of an ac'cident, does not involve a significant decrease in a safety margin, and, therefore, does not involve a significant hazards consideration.
We have also concluded that there is reasonable assurance that the health and safety of the public wil 1 not be endangered by this action and that the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
A copy of the Notice of Issuance is also enclosed.
Sincerely Enclosures and cc:
See next page enny M. Crutchfield, C
ef Operating Reactors Branch 85 Division of Licensing
Enclosures:
l.
Amendment No. 35 to License No.
DPR-18 2.
Notice. of Issuance cc w/enclosures:
See page 4
l I
Nr. Leon D. Mhite, Jr.
cc w/enclosures:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and HacRae 1333 New Hampshire Avenue, N. M.
Suite 1100 Washington, D. C.
20036 Nr. Nichael Slade 12 Trailwood Circle Rochester, New York 14618 Rochester Coomittee for Sci entific Information Robert E. Lee, Ph.D.
P. 0. Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza
- Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 Supervisor of the Town of Ontario 107 Ridge Road West
- Ontario, New York 14519 Resident Inspector R. E. Ginna Plant c/o U. S.
NRC 1503 Lake Road
- Ontario, New York 14519 Ezra !. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)
U. S. Environmental Protection Agency Washington, D. C.
20460 U. S. Environmental Protection Agency Region II Office ATTN:
EI S COORD INATOR 26 Federal Plaza New York, New York 10007 Herbert Grossman, Esq.,
Chairman Atomic Safety and Licensing Board U-S. Nuclear Regulatory Coranission Washington, D. C.
20555 Dr. Richard F. Cole Atomic Safety and Licensing Board U. S. Nuclear Regulatory Cormission Washington, D. C.
20555 Dr.
Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Mashington, D. C.
20555 Hr. Thomas B. Cochran Natural Resources Defense Council, Inc.
1725 I Street, N. M.
Suite 600 Washington, D. C.
20006