ML17309A183
| ML17309A183 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/27/1981 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17309A182 | List: |
| References | |
| NUDOCS 8109090398 | |
| Download: ML17309A183 (42) | |
Text
APPENDIX A
, REPORT RADIOACTIVE EFFLUENTS FACILITYc ROCHESTER GAS 4
LECTRIC GINNA STATION DOCKET:
50 244 YEAR<
1981 I ~
LIQUID RELEASES I ~
GROSS RADIOACTIVITY 8
UNITS JAN FEB ~
MARCH APR I I.
MAY JUNE TOTAL A ) TOTAL RELEASEO (exes t 2 3
d 4 )
8 ) AVERAGE CONCENTRATION RELEASEO CURIES CI/ML 3.52E3 162 f 3 132 E
Si07 E7 498 E
7 122 f-6 5
67 E
05 E6 5
f 3 7
39 E
5 2
11 E
2 N/A 25 f 61986 0 1 MAXI MUM CONCENTRATION REI.EASED 0 I ML 26 E6 I ~ 33 E6 3 ~ 19 6'5 I
I E
5 3
5 f-5 4 06 E
5 N/A 2
TRITIUM A ) TOTAL RELEASEO CURIES 6 ~ 6 2 +71 12 5
48 03 43 8
21 64 135 e28 8 ) AVERAGE CONCENTRATION RELEASEO C ) PERCENT OF LIMIT 3.
OISSOLVEO NOBLE GASES 0 I /ML 1.22E7513E82 I
E7 0 004 0 e007 0 002 9i26 E
7 0 e031 0 043 0
O'17 1.3E6 496 E7 H/A H/A A ) TOTAL RELEASEO 8 ) AVERAGE CONCENTRATION RELEASEO 4
GROSS ALPHA RADIOACTIVITY A ) TOTAL RELEASEO '
) AVERAGE CONCENTRATION RELEASED CUR I ES 0 I /ML CORI ES 11CI/ML ND NO ND ND HO NO NO NO ND HO NO NO N
A NO N/A 5.
VOLUME OF L I Ulo WASTE TO DISCHARGE CANAL 6
VOLUME OF DILUTION 'WATER 7
ISOTOPES RELEASEO Cerium li'I Ruthenium 103 Cesium
'137 Cue)urn 134 Cobol t'8 LITERS LITERS CUR I ES ND ND NO NO HO NO 124 E-32.21E4 395 E5 I
10 E-3 87 Ei 287 Ei I 42 E>>5 4 ~ 32 E 6 6 ~ 52
'E 4
3.88 E 6 3~77 f 6 3.46 E 6 5
37 E
10 5 28 E
10 5 98 E
10 275 E6 5
19 E
10 NO NO 291 E3 1.94 E
3
'3 ~79 E-6 7,37 E
5 4
I E
6 1,87 E
7 3 ~ 38 E
10 4 36 E
10 2 96 Ell 7
1 E 6 7
I E
NO NO ND 8
6 E-i 4.47 E
3 9 74 E-3 2,65 E
4 181 E
3 6 27 E
3 5 ~ 38 E
5 9 0 f 5 8
18 E-4 Cobalt 60 1.49 E
'5 5,25 E-4 NO I
13 E-4 3.4 E
4 1.01 E
3 2e00 E
3'nn enese 54 Zircon)un 95 Hloblum 95 ND NO HD NO ND NO 967 E
5 NO NO NO NO ND NO NO NO 1,0 E
5 1,07 E<<i ND NO Cerium 144/Pressed mlum lil Tel lur lcm 132 Ruthenium 106 Sliver 110m Mol bdenum 99 Berlum 140 Chromium 51 Iron 59 Tellurium 129m Cesium 136 Ne tunlum 239 Iodine 131 Tellurium 127m Bur Ium/Lenthenum 140 Zinc 65 Strontium 90 Ant lmon 125 PRECENT OF TECHNICAL SPECIFICATION LIMIT FOR ACTIVITY RELEASEO ee 3
6 E
4 NO ND NO ND ND ND NO NO NO NO 781 E
NO NO NO NO HO 0.005 NO NO NO NO ND NO NO NO NO NO HD ND NO NO
<0 001 2.47 E
4 NO NO NO NO NO NO ND NO ND NO NO NO NO NO NO ND
<0.001 7.0 E
NO NO HO NO NO NO NO NO NO ND NO ND ND ND 0 005 NO NO NO NO NO NO ND HD NO ND ND NO NO NO NO
<0 001 ND NO ND HO NO NO NO NO NO NO NO NO NO NO NO ND 0 o001 I e31 f-3 NO NO NO NO NO NO NO NO NO ND 7
81 E-4 NO ND NO ND N/A 81090903')18 8i0827 PDR ADOCK 05000244-R PDR
~~~ ~P APPENDIX A REPORT RADIOACTIVE EFFLUEHTS FACILITY; ROCHESTER GAS 6
ELECTRIC GINHA STATION DOCKET:
50 244 YEAR:
1981 I I ~
AIRBORNE RELEASES I
TOTAL NOBLE GASES 2
TOTAL HALOGENS 3e TOTAL PARTICULATE GROSS RAG IOACTIV ITY
(
UH I TS CUR I ES CURIES CURIES JAN ~
40.56 FEB 45 I ~35E72 37E7 662 E51
~155 MARCH 67 64 I e54 E
5 5 99 E
7 APRIL 105 o8 MAY 68 23 JUNE 5
E 4
4+23 E
I 09 E
2,6E7123E61.346 TOTAL 347 33 88 E
3e6 E6 4 ~
TOTAL PARTICULATE CROSS ALPHA RADIOACTIVITY CURIE S CUR I ES NO 00 1,81 5
13 HO 2 F85 NO NO 2 82 NO 27 F 11 ND 6
MAXIMUM NOBLE GAS RELEASE RATE 7. PERCEHT OF APPLICABLE LIMIT FOR:
A I NOBLE GASSES 8 ) HA'LOGEHS C ) PARTICULATES 0 I/SEC 230 106 ~
0.027 0.032 0 028 0.035
<0,0001
<0 0001 165 0 051 0 037
<<0 o0001 1610
~
0 055 0 ~ 39
<0 +0001 1580
~
0,043 0 +68 0.0002 28 0 ~ 015 0.076 0 +0009 N/A H/A H/A N/A 8
ISOTOPE RELEASEO:
PARTICULATES Ceslua 137 Cobslt 60 CUR I ES NO NO NO NO 1.21 E
7 I 29 E
7 7,85E7244E79
~33E7 6
3 E 7 4
47 E
7 I ~ 14 E
6 I
~ 15 E
6 2 35 E
6 Bsrlun Lsnthsnue 140 ND NO-ND ND NO 655E7 6
55 E-7 Cobalt 58 Ceslun 134 Ruthenlun 103 NO ND NO ND NO NO NO ND NO 26 E
7 NO 271 E
7 1.86E7 7 ~5E8 345 68 ND 114 E7 ND 5.97 E-7 2.96 E
7 14 E7 Antisun 125 Nloblue 95 Chroelun 51 I od Inc
'I 51 HALOG'ENS CUR IES NO ND ND ND NO NO NO NO I
72 E7 NO NO NO NO 5 03 E
8 NO ND NO NO NO ND NO 1+2 E
6 3.66 E-7 I 72 E-7 5 03 E
8 12 E6 o66 E
'I 32 2 69 E-5 1+95 E
5 HO NO 288 E
5 NO 292 E453E457E5 I 34 E
4 5
7 E'D 9.54 E
4 3 F83 E
5 9 56 E5 NO ND 1.25 E
NO I ~58 E
NO NO NO 5 ~ 17 E
5 NO 4,7 E
NO GASES Xenon 135m Ar on 41 Xenon 133m Xenon 131M Xenon 133 Kr ton 85 Xenon 135 Kr ton 85n Kr ton 87 Kr ton 88 Xenon
'158 CUR I ES 0
108 0 024 0 013 0 027 38 6
0,434 1+29 0 015 0.015 0.026 0.010 0 '99 0.024 0 004 3.21 36+2 0.507 2
31 0.01'I 0 014 0.014 0 +013 0 ~073 0 '63 NO ND 60 ND 5
9 0
142 0.005 0 009 I
161 0,027 0 ~ 30 0.29 2,80 90 5
7,20 4.69 0.005 0,012 0 004 0.002 ND ND HO 0
'14 67.45 0.64 NO NO ND NO 0 +028 0 e009 0 /002 O,II 17 95 2.49.
I
'10 0 o003 0.003 0 004 0.003 0 335 0 +62 0 309' 287 310.8 11.271 15 29 0
175 0 049 0 057 I ~ 189 OTHERS AS APPROPRIATE
(
SPECIFY CUR I ES
~
4,
Docket No.
50 219 0 2 SEE ATTACHED LISTING UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON 0;C. 20555
,June 12, 1981 UT40
'kets (2)
ORB HSmith Oyster Creek Nuclear Power P)ant located in Ocean County, NJ R. E. Ginna Nuc1ear Power P1ant located in Wayne County, NY The following documents concerning our review of the subject facility are transmitted for your information:
Notice of Receipt of Application.
Draft/Final Environmental Statement, dated Q
Safety Evaluation, or Supplement No.,dated Notice of Hearing on Application for Construction Permit.
Notice of Consideration of Issuance of Facility Operating License.
Application and Safety Analysis Report, gol.
Amendment No.
to Application/SAR, dated Construction Permit No. CPPR
,date Facility Operating License Nn. DPR-, NPF-
, date Amendment No.
to CPPR-or DRR-,dated ot.
1 } Monthly operati ng report f'r 5/8 1 dated 5/1 8/81
- 2) Annual report of changes to station facil ies
& procedures dtd. 4/29/81
Enclosures:
As stated cc:
0 tce of clear Reac or Regulation Division of Licensing Operating Reactors Branch 85 JUN 16 1S81 DFFeep-
~RB Nl HSmit :rj SURNAME ~
DATE ~
NRC 2I (6.76) 6/
/81
h 11 rv..'t ~ ~ vgt.
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Chief Division of Ecological Services Bureau of Sport Fisheries and Mildlife U. S.
Department of the Interior Mashington, D.
C.
20240 Director National Oceanographic Data Center Environmental Data Service National Oceanic II Atomospheric Administration U. S.
Department of Commerce Mashington, D.
C.
20234 Dr. Milliam B. Stroube, Jr.
FDA Research Chemist National Bureau of Standards Reactor Building 235, Rm. B108 Mashington, D.
C.
20234 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)
U. S. Environmental Protection Agency Mashington, D. C.
20460
~EPA R
U..S. Environmental Protection Agency Region II Office ATTN:
EIS COORDINATOR 26 Federal Plaza New York, New York 10007
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SECRETARY.
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'UCLEAR REGULATORY COMMlSSlON-WASHINCZON, QA 20555 April 21, 1981
'irector Office of the Federal Registet
'National Archives and Records Seryice Washington, D. C.
20403
Dear Sir:
Enclosed for publication in the Federal Register are an original and two certified copies of a document entitled:
Rochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant,'50-244 Order: for Modification of License This material is to be charged to requisition number 6-132, JN 340-371.
Sincerely, e
0, Chi Secretary of k
he Commission
Enclosures:
Original and 2 certified copies I
'h bcc:
Record Services Branch Office of Public Affairs Executive Legal Director Office of Congressional Affairs 0ffice of the General Counsel
lo
7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Natter of ROCHESTER GAS 5 ELECTRIC CORP.
R. E. Ginna Nuclear Power Plant Docket No. 50-244 ORDER FOR MODIFICATION OF LICENSE I
The Rochester Gas and Electric Corporation (the licensee) holds Provisional Operating License No. DPR-18, which authorizes the licensee to operate the R.
E. Ginna Nuclear Power Plant (the facility) at power levels not in excess of 1520 megawatts (thermal) rated power.
The facility, which is located at the licensee's site in Wayne County, New York is a pressurized water reactor (PWR) used for the cormercial generation of electricity.
The Reactor Safety Study (RSS),
WASH-1400, identified in a PWR an inter-system loss of coolant accident (LOCA) which is a significant contributor to risk of core melt accidents (Event V).
The design examined in the RSS
~ contained in-series check valves isolating the high pressure Primary Coolant System (PCS) =from the Low Pressure Injection System (LPIS) piping.
The scenario which leads to the Event V accident is initiated by.the failure of these check valves to function as a pressure isolation barrier.
This causes an overpressurization and rupture of the LPIS low pressure piping which results in a LOCA that bypasses containment.
f t
~ 7.590-01 In order to better define the Event V concern, all light water reactor licensees were requested by letter dated February 23, 1980, to provide the following in accordance with 10 CFR 50.54(f):
1.
Describe the va1 ve configurati ons and indicate if an Event V isolation valve configuration exists within the Class I boundary of the high pressure piping connecting PCS piping to low pressure system piping; e.g.,
(1) two check valves l
in series, or (2) two check valves in series with a motor operated valve (NOV);
- 2. If either of the above Event V configurations exist, indicate whether continuous surveillance or periodic tests are being performed on such valves to, ensure integrity.
Also indicate whether valves have been known, or found, to lack integrity; and
- 3. If either of the above Event V configurations exist, indi cate whether'lant procedures should be revi sed or if plant modifications should be made to increase reliability.
In addition to the above, licensees were asked to perform individual check valve leak testing prior to plant startup after the next scheduled outage.
By letter dated Narch 14, 1980, the licensee responded to our February.-
letter.
Based upon the review of this response as well as the review of previously docketed information for the facility, I have concluded in con-sonance with the attached Safety Evaluation (Attachment
- 1) that one or more valve configuration(s) of concern exist at the facility.
The attached Tech-nical Evaluation Report (TER) (Attachment
- 2) provides, in Section 4.0, a
tabulation of the subject valves.
7590-01 3
The staff's concern has been exacerbated due not only to the large number of plants which have an Event V configuration(s) but also because of recent unsatisfactory operating experience.
Specifically, two plants have leak tested check valves with unsatisfactory results.
At Davis-Besse, a pressure isolation check valve in the LPIS failed and the ensuing investigation found that valve internals had become disassembled.
At the Sequoyah Nuclear Plant, two Residual Heat Removal (RHR) injection check 4
valves and one RHR recirculation check valve failed because valves jammed open against valve over-travel limiters.
It is, therefore, apparent that when pressure isolation is provided by two in-series check valves and when failure of one valve in the pair can go undetected for a substantial.length of time,'erification of valve integrity is required.
Since these valves are important to safety, they should be tested periodically to ensure low probability of.gross Failure.
As a result, I have determined that periodic examination of check valves must be undertaken by the licensee as provided in Section III below to verify that each valve is seated properly and functioning as a pressure isolation device.
Such testing will reduce the overall risk of an inter-system LOCA.
The testing mandated by this Order may be accomplished by direct volumetric leakage measurement or by other equivalent means capable of demonstrating that leakage limits are not exceeded in accord-ance with Section 2.2 of the attached TER.
4 In view of the operating experiences described above and the potential consequences of check valve failure, I have determined that prompt action is necessary.to increase the.level of assurance that multiple pressure'solation barriers are in place and will remain intact.
Therefore, the public health, safety and interest require that this modification of Provisional Operating License No. DPR-18 be immediately effective.
Accordingly, pursuant to Section 16li of the Atomic Energy Act of 1954, as
- amended, and the Comnission's regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED THAT EFFECTIVE IMMEDIATELY, Provisional Operating License~
No. DPR-18 is modified by the addition of the following requirements:
1.
Implement Technical Specifications (Attachment
- 3) which require periodic surveillance over the life of, the. plan; and which
'l ~
specify limiting conditions for operation for PCS pressure isolation valves.
- 2. If check valves have not been (a ) individually tested within 12 months preceding the date of the Order, and (b) found to comply with the leakage rate criteria set forth in the Technical Specifications described in Attachment 3, the MOV in each line shall be closed within 30 days of the effective date of this Order and quarterly Inservice Inspection (ISI). MOV cycling ceased until the check valve tests have been satisfactorily accomplished.
(Prior to closing the MOV, procedures shall be implemented and operators trained to assure
that the HOV remains closed.
Once closed, the HOV shall be tagged closed to further preclude inadvertent valve opening).
3.
The HOV shall not be closed as indicated in paragraph 2 above unless a
s upporting safety evaluation has been prepared.
If the HOV is in an emergency core cooling system (ECCS), the safety evaluation shall include t
a determination as to whether the.requirements of 10 CFR 50.46 and Appendix K to 10 CFR Part 50 will continue to be satisfied with the HOY closed.
If the HOY is not in an ECCS, the safety evaluation'hall include a deter-mination as to whether operation with the HOV closed presents an,unreviewed safety question as defined in 10 CFR 50.59(a)(2).
If the requirements of 10 CFR 50.46 and Appendix K have not been satisfied, or if an unreviewed safety question exists as defined in 10 CFR 50.59, then the facility shall'e shut down within 30 days of the date of this Order and remain shutdown until check valves are satisfactorily tested in accordance with the Techni-cal Specifications set forth in Attachment 3.
4.
The records of the check valve tests required by this Order shall be made available for inspection by the HRC's Office of Inspection and Enforcement.
4
~
~
7590-01 IV The licensee or any other person who has an'interest affected by this Order may request a hearing on this Order within 25 days of its publication in the Federal
~Re ister.
A request for hearing shall be submitted'to the Secretary, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.
A copy of the request shall also be sent to the Executive Legal Director at the same
- address, and to Harry H. Voigt, Esquire,
- LeBoeuf, Lamb, Leiby 8
- MacRae, 1333 New Hampshire Avenue, N.
W. Suite 1100, Washington, D. C.
- 20036, attorney for the licensee.
If a hearing is requested by a person other than the licensee, that person shall describe, in accordance with 10 CFR 2.714(a)(2),
the manner in which his or her interest is affected by this Order.
ANY REQUEST FOR A HEARING SHALL NOT STAY.THE IMMEDIATE EFFECTIVENESS OF THIS ORDER.
'f a hearing is requested by the licensee or other person who has an interest affected by this Order, the Commission will issue an order designating the time and place of any such hearing.
If a hearing is held, the issues to be considered at such a hearing shall be:
(a) Whether the licensee should be required to individually leak test check valves in accordance with the, Technical Specifications set forth in Attachment 3 to this Order.
(b) Whether the actions required by Paragraphs 2 and 3 of Section III of this Order rmst be taken if check valves have not been tested within 12 months preceding the date of this Order.
~
~
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~
~
7590-01 Operation of the facility on terms consistent with this Order is not stayed by the pendency of any proceedings on this Order.
In.the event that a
need for further action becomes
- apparent, eitheI in the course of
,proceedings on this Order or any other time, the Director will take appropriate action.
R THE NUCLEAR REGULATORY COMMISSION
\\ ~
,Effective Date:
April 20, 1981
- Bethesda, Mary 1 and hu D
Darrell G
- sen, irector Division of icensing Attachments:
1.
Safety Evaluation Report 2.
Technical Evaluation Report 3.
Technical Specifications
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OFFICE OF THE SECRETARY UN)TEDSTATES NUCLEAR REGULATORY COMMISSION-WASHINGTON,D.C. 20555 April 8, 1981 Director Office of the Federal Register National Archives and Records Seryice Washington, D. C.
20403
Dear Sir:
Enclosed for'ublication in the Federal Register are an original and two certified copies of a'document entitled:
ROCHESTER GAS AND ELECTRIC CORPORATiON Docket No. 50-244 t)OTICE OF ISSUANCE OF 'AIIEt'Dh'IENT TO PROVISIONAL OPERATING LICENSE Publication of the above document at the earliest possible date would be appreciated.
This material is to be charged to requisition number G-132, JN 340-371.
Sincerely,
)
/
/~
~Sa e
J. Chilk Secretary of the Commission l
Encl osures:
Original and 2 certified copies bcc:
Record Services Branch Office of Public Affairs Executive Legal Director Office of Congressional Affairs Office of the General Counsel
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 Commission (the Commission) has issued Amendment No.
39 to Provisional Operating License No.
DPR-18, issued to Rochester Gas and Electric Corporation (the licensee),
which revised the Technical Specifications for operation of the R.
E. Ginna Nuclear Power Plant (the facility) located in Wayne County, New York.
The amendment is to become effective June 30, 1981.
The amendment modifies the Technical Specifications to reflect modifi-cations of the Fire Protection System being completed at the facility.
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 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.
Prior public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.
The Commission 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 declara-tion and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
QDt V
7590-01 For further details with respect to this action, see (1) the application for amendment notarized February ll, 1981 (submitted by letter dated February 13, 1981),
and (2) Amendment No.
39 to License No.
DPR-18, including the Commission's letter of transmittal.
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 item (2) may be obtained upon request addressed to the U ~ S.
Nuclear Regulatory Coranission, Washington, D.C.
20555, Attention:
Director, Division of Licensing.
Dated at Bethesda, Maryland, this first day of April, 1981.
FOR THE NUCLEAR REGULATORY COMMISSION ennis M. Crutc ield Chief Operating Reactors Branch P5 Division of Licensing
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~Isis RE/II, P
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++*++
OFFICE OF THE SECRETARY UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON,D.C. 2D555 Apri1 6, 1"81 Director Office of the Federal, Register National Archives and Records geryice Washington, D. C.
20403
Dear Sir:
Enclosed for publication in the Federal Register are an original and two certified copies of a document entitled:
ROCHESTER GAS lIÃD ELECT"IC CC.".PORATIOH Docket.I'Io.60-244 NOTICE Of ISS"AtICE OF AHEHD~IEh! 70 PROVIS,'GHA'."EPA: IHG LICFHSE Publication of the above document at the earliest possible date would be appreciated.
This material is to be charged to requisition number G-132, JH 340-371.
Sincerely, I
/~
I g
~Samue J. Chilk Secretary of the Commission
l
Enclosures:
Original and 2 certified copies b~cc:
Record Services Branch Office of Public Affairs Executive Legal Director Office of Congressional Affairs Office of the General Counsel
UNITED STATES NUCLEAR REGULATORY COHHISSION DOCKET NO. 50-244 ROCHESTER GAS AND ELECTRIC CORPORATION NOTICE OF ISSUANCE OF AHENDHENT TO PROVISIONAL OPERATING LICENSE The U.
S. Nuclear Regulatory Commission (the Commission) has issued A-.iendment No. 38 to Provisional Operating License No.
DPR-18, to Rochester C:-s and Electric Corporation (the licensee),
which revised the technical s=ecifications for operation of'he R.E.
Ginna Plant (facility) located
- i. l ayne County, New York.
This amendment is effective as of the date o-. its issuance.
Tne amendment incorporates limiting conditions for operation and s.rveillance requirements regarding degraded grid voltage protection for t~e Class 1E power system.
ihe application for the amendment complies with the standards and r=quirements of the Atomic Energy Act of 1954, as amended (the Act), and t;e Commission's rules and regulations.
The. Commission has made appro-p.-iate 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
.amend-m=n-.
Prior public notice of this amendment was not requi red since the a-.endm nt does not involve a significant hazards consideration.
The Commission has determined that the issuance of this amendment w.ll not result in any significant envi ronm ntal impact and that pursuant 1 0 CFR 551
. 5(d) (4) an envi ronmental impact statement or negati ve c=-c;aration and environmental impact appraisal need not be prepared i,. connection with issuance of this amendment.
7590-01 For further details with respect to this action, see (1) the application for amendment dated September 9,
1980 (.ransmitted by letter dated September 15, 1980),
as preceded and supported by submittals dated July 21,
- 1977, November 21, 1977, December 16, 1977 (transmitted by letter dated December 22, 1977), July 31, 1979 (transmitted August 3, 1979 - two separate submittals),
and December 19,
- 1979, (2) Amendment No.
38 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.M., 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, f<aryland, this 26th day of March, 1981.
FOR THE NUCI EAR REGULATORY COMMISSION z.g Dennis N. Crutchfield, ie Operating Reactors Branch P5 Division of Licensing
tyy'
'tr
UNITEDSTATES h
NUCLEAR REGULATGRY COMMISSION WASHINGTON, D.C. 20555 OFFICE OF THE SECRETARY March 16, 1"=Qj Director Office of the Federal Register National Archives and Records Setyjce Washington, D. C.
20403
Dear Sir:
Enclosed for publication in the Federal Register are an original and
'wo certified copies of a document entitled:
ROCHESTER GAS,AtID ELECTRIC CORPGRATIOI'I Docket No.
SG-244 NOTICE OF ISSUANCE OF At",ENDHEtlT TO OPERATING LICENSE.
e Publication of the above document at the earliest possible date would be a ppreci a ted.
This material is to be charged to requisition number G-132, Jt) 340-371.
Sincerely, I
r
'I "Samuel.
Chil k Secretary of the Commission I
Encl o sures:
l3 iginal and 2 certified copies bcc:
ecord Services Branch Office of Public Affairs Executive Legal Director Office of Congressional Affairs Office of the General Counsel
UNITED STATES NUCLEAR RFGULATORY COMMISSION DOCKET NO. 50-244 ROCHESTER GAS AND ELECTRIC CORPORATION NOTICE OF ISSUANCE OF AMENDMENT TO OPERATING LICENSE The V. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No.
37 to Provisional Operating License No.
DPR-18 to Rochester Gas and'lectric Corporation (the licensee) which revised the license for operation of the R.
E. Ginna Nuclear Plant.located in Mayne County, Hew York.
The amendment is effective as of the date of issuance and the portion relating to Safeguards Contingency is to be fully implemented within 30 days of Commission approval in accordance with the provisions of 10
'CFR 73.40(b).
The amendment adds a license condition to include the Commission-approved Safeguards Contingency Plan as part of the license, and revises the license condition relating to the Security Plan to incorporate approved changes.
The licensee's filings comply 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 appropriate findings as required by
.he Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Prior publi.c notice of this amend-ment was not required since the amendment does not involve a significant hazards consideration.
~ p
2-The Commission 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 need not be prepared in connection with issuance of the amendment.
The licensee's filings (transmitted by letters dated April 3, 1980, July 24, 1980, and September 10, 1980) are being withheld from public disclosure pursuant to 10 CFR 2.790(d).
The withheld information is sub-ject to disclosure in accordance with the provisions of 10 CFR 59.12.
For further details with respect to this action, see (1) Amendment No.
to License No. 'DPR-18, and (2) the Commission's related letter to the licensee dated March ll
, 1981.
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 14527.
A copy of items (1) and (2) 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, thi s 11th day'f March, 1 981.
FO THE NUCLEAR REGULATORY COMMISSION
~. Q1~J Dennis M. Crutchfield, ef Operating Reactors Branch N5 Division of Licensing
4'