ML021230327
| ML021230327 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 04/30/2002 |
| From: | Balduzzi M Vermont Yankee |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BVY 02-27, FOIA/PA-2007-0068 | |
| Download: ML021230327 (25) | |
Text
VERMONT YANKEE NUCLEAR POWER CORPORATION 185 OLD FERRY ROAD, PO BOX 7002, BRATTLEBORO. VT 05302-7002 (802) 257-5271 April 30, 2002 BVY 02-27 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Vermont Yankee Nuclear Power Corporation, Entergy Nuclear Vermont Yankee, LLC, and Entergy Nuclear Operations, Inc.
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
Transfer of Facility Operating License - Revised Paaes This submittal provides a complete revised copy of license and TS pages to reflect comments provided by your Staff on our previous submittals. This is intended to replace the previously submitted mark-up and re-typed versions (Enclosure 1, Attachments A & B) in their entirety.
The changes are editorial and no new technical changes are proposed, thus the original no significant hazards consideration is still valid and does not require revision.
If you have any questions concerning this transmittal, please contact Mr. Jeffrey T. Meyer at (802) 258-4105.
Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION Michael A. Balduzzi Senior Vice President and Chief Nuclear Officer Enclosures cc:
USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS Vermont Department of Public Service
/y-cog
BVY 02-27 / page 2 For Vermont Yankee Nuclear Power Corporation:
Michael A. Balduzzi Senior Vice President and Chief Nuclear Officer STATE OF VERMONT
)
)ss WINDHAM COUNTY
)
Then personally appeared before me, Michael A. Balduzzi, who being duly sworn, did state that he is Senior Vice President and Chief Nuclear Officer of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoing document in the name and onl behalf of Vermont Yankee Nuclear Power Corporation, and that the statement therein are true to the best of his knowledge and belief.
SAN Saily4. Sandstrur, Notary Public My Commission expires February 1 003
BVY 02-27 / page 3 For Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear 0 erAt ns:
haX6d k. kasg e Date State of (County of Then personally appeared before me, Michael R. Kansler, who being duly sworn, did state that he is Senior Vice President and Chief Operating Officer of Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc., that he is duly authorized to execute and file the submittal contained herein in the name and on behalf of Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc., and that the statements attributable to Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. are true to the best of his knowledge and belief.
My commission expires:
Aý2A~
r Date Notary Public PATRICIA L. TERRY Notary Public, State of New York No. 4991258 Cualified in WestchesterCountyY Commission Expires Jan. 27. 2012.Q Attachment A
UITCD STATrS ATOMIC ENERGY COMMiSSION "WASetpGI*,T. O.C.- 3054S (Vermont Yankee Nuclear Power Station)
Docket No. 50-271 Facility Operating License License No. DPR-28 Amendment No.
5 The Atomic Energy Commission (the Commission) having found that:
- a.
Construction of the Vermont Yankee Nuclear Power Station (the facility) has been substantially completed in conformity with the application, as amended, the Provisional Construction Permit No.
CPPR-36, the provisions of the Atomic Energy Act of 1954, as amended (the Act), and the rules and regulations of the Commission as set forth in Title 10, Chapter 1, CFR; and
- b.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; and
- c.
There is reasonable assurance (1) that the activities authorized by this amended operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission, and LLC. Is 47AVr;,1 CL"-.J~ieActtca e NQ1LetsV N ' ~
- d.
'~emn ake uc e rPwer 96rporqfion kfermot Ya~ee i
technically and financially qualified to. engage. in the activities l author'ized by this amended operating license, in accordance with the iV otrules and regulations of the Commission; and
- e.
Vermont Yankee satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and -Indemnity Agreements" of the Commission's regulations; -and C. The issuance of this amended operating-license will not be inimical to the common defense and security or to the health and safety of the public; and
- g.
After weighing the environmental, economic, technical and other benefits of the facility against environmental costs and considering available alternatives, the issuance of this amended operating license (subject to the conditions for protection of the environment set forth herein) is in accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirements of
- 4%%
said Appendix D have been satisfied.
AL\\cordingly, Facility Operating Lice
- o. DPR-28, as amended, issued to Vermont Yankee(Nu-ear owerYorp atio (Vernt YaEee), is hereby amended in its entirety to read:
k-LLC V
'-vj Fudeore 0?
C-IM.
- 1.
This license applies to the Vermont Yankee Nuclear Power Station (the facility), a single cycle, boiling water, light-water moderated and cooled reactor, and associated electric generating equipment.
The facility is located on eon Yan e'ssite, in the Town of Vernon, Windham County, Vermonttand is described in the application as amended.
t 4q-rs a.3ucer.,w VcrM L.LC5'
- 2.
Subject to the Conditions and re uirements incorporated herein, the Commission hereby licenses t ap *lcn:
6^+"13 A.
Pursuant to Sections 104b of the Atomic (Energy Act of 1954, as amended (the Act), and 10 CFR Part 50,
'Licensing of Production and Utilization Facilities," to possessouse, and operate the as faciutilization fatility at the designated location on the 6e Ioni/Yan _e~e site.
L.Ev%+r3 rZ'cde."
Vqvwrv4%A
'Iaviikec B. Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation as described in the Final Safety Analysis Report, as supplemented and amended.
SPursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess, and use at an*y time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for calibration of reactor instrumentation and radiation monitoring equipment, and as fission detectors in amounts as required.
D Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and tje in amounts as required any byproduct,
- source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components.
0 ~ecLr L.L.C I-L A-31 2.14.7 r=ftJr.r!),J iQVkCkC0.e E. Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.
- 3. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and 6rders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A. Maximum Power Level Et4rv-1 4 q.L
- rC
, 1*.
V eon Ya~ee is authorized to operate the facility at reactor core power levels not to exceed 1593 megawatts thermal in accordance with the Technical Specifications (Appendix A) appended hereto.
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through nt**
5, are hereby incorporated in the license. ghtflcen
ýeshall operate the facility in accordance with the Technical Specifications.
Ve kon Ya ke shall e reports in accordance with the requirements of the echnical Specifications.
Records 4
on Yarce shall keep facility operating records in accordance withP terquirements of the Technical Specifications.
E. Environmental Conditions Pursuant to the Initial Decision of the presiding Atomic Safety and Licensing Board issued February 27, 1973, the following conditions for the protection of the environment are incorporated herein:
C.
D.
I Podn ND. 206
- 1. This paragraph deleted by Amendment No.206, October22,2001.
- 2.
This paragraph deleted by Amendment No. 131, 10/7/91.
- 3.
This paragraph deleted by Amendment No. 206,October 22,2001.
- 4.
If harmful effects or evide e of irreversible damage in land or water eco stems as a result of facility operation are detected by&
2 ic se's environmental'monitoring program, o on Y
eepshall provide an analysis of the problem to the Cormmsi and to. the advsory group for the Technical Specifications, thereafter will provide, subject to the rene a oresai advisory group, a course of action be taken immediately to alleviate the problem.
l
- 5.
e will grant authorized representatives of the Massacu setts Department of Public Health (MDPH) and Metro politan District Commission (MDC) access to records and charts related to discharge of radioactive materials to the Connecticut River.
- 6.
This paragraph deleted by Amendment No.
206, October 22,-2001.
Amendment No. 206 I
I I
- 7.
This paragraph deleted by Amendment No. 206 October 22, 2001.
- 8.
t
ý-ewill permit authorized representatives of the MDPH an-MDC to examine the chemical and radioactivity analyses performed by4eXon"
- 9.
a shall immediately notify MDPH, or an agency designate
- MDPH, in the event concentrations of radioactive materials in liquid effluents, measured at the point of release from Vermont Yanke exceed the limit set forth in the facility Offsite Dose lculation Manual.
Q2Lmo_ Yaee will a so notify MDPH in writing within 30 days following the re ease of radioa tive materials in liquid effluents in excess o 10 percent of he limit set forth in the facility Offsite D se Calculation anual.
-the f04 j
- 10. A report shall be submitted to MDPH and MDC by May 15 of each year of plant operation, specifying the total quantities of radioactive materials released to the Connecticut River during the previous calendar year.
The report shall contain the following information:
(a) Total curie activity discharged other than tritium and dissolved gases.
(b) Total curie alpha activity discharged.
(c) Total curies of tritium discharged.
(d) Total curies of dissolved radio-gases discharged.
(e) Total volume (in gallons) of liquid waste discharged.
Amendment No. 206 (f) Total volume (in gallons) of dilution water.
(g) Average concentration at discharge outfall.
(h) This paragraph deleted by Amendment No. 206,0ctober 22, 2001.
(i) Total radioactivity (in curies) released by nuclide including dissolved radio-gases.
(j) Percent of the facility Offsite Dose Calculation Manual limit for total activity released.
- 11. This paragraph deletdd by Amendment No.
206
- October 22, 2001.
- 12.
This paragraph deleted by Amendment No. 206 October 22i 2001.
~.ri-3'A CjV.ri-op4ev-ý'Vs lv~c'.
- 13. Vmont e
shall establish and maintain a system of emergeincy notfication to the states of Vermont and New Hampshire, and the Commonwealth of Massachusetts, satis factory to the appropriate public health and public safety officials of those states and the Commonwealth, which provides for:
- a.
Notice of site emergencies as well as general emergencies.
- b.
Direct microwave communication with the state police headquarters of the respective states and the Common wealth when the transmission facilities of the respective states and the C mmonwealth so permit,_t the ex-pse of &efont/Yan ee Amendment No. 206
4 'S55 ijv.g
:-
- c.
A verification or cod stem for emergency messages between ontYa and the state police headquarter~s of the respective states and the Commonwealth.
t rcler"R W
.kce.
tr C.
- 14. Jjt/Y
- ee shall furnish advance notification to DPE ort6other Commonwealth agency designated by MDPH, of the time, method and proposed route through the Commonwealth of any shipments of nuclear fuel and
- M wastes to and from the'Vermont Yankee facility which
", Irc. will utilize railways or roadways in the Commonwealth.
F.;
ee shall implement and maintain in effect all I rovTs-ons o the approved Fire Protection Program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated January 13,
- 1978, and supplemental SERs, dated 9/12/79, 2/20/80, 4/15/80, 713/80, 10/24/80, 11/10/81, 1/13/83, 7/24/84, 3/25/86, 12/1/86, 12/8/89, 11/29/90, 8/30/95, 3/23/97, 6/9/97, 8/12/97, 3/6/98, 3/31/98, 9/2/98, and 2/24/99, subject to the following provisions:
ýe n
ý may make changes to the approved Fire Proram without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
G. Security Plan en e shall fully implement and maintain in effect a
provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to IOCFR73.55 (51FR27817 and 27822) and to the authority of 10CFR50.90 and 10CFR50.54(p).
The plans, which contain Safeguards Information protected under IOCFR73.21, are entitled:
"Vermont Yankee Nuclear Power Station Physical Security Plan," with revisions submitted through March 16, 1988; "Vermont Yankee Nuclear Power Station Training and Qualification Plan," with revisions submitted through November 10, 1982; and "Vermont Yankee Nuclear Power Station Safeguards Contingency Plan," with revisions submitted through December 30,. 1985.
Changes made in accordance with IOCFR73.55 shall be implemented in accordance with the schedule set forth therein.
Amendment No. 206 SA-1-68 H. This paragraph deleted by Amendment No. 107, 8/25/88.
I. This-paragraph deleted by AmendmentNo. 131, 10/7/91.
- 4. This license is effective as of the date of issuance and shall expire at midnight on March 21, 2012.
FOR THE ATOMIC ENERGY COMMISSION Original Signed By Roger S. Boyd /f/
A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing iA-127 12/17/90
Enclosures:
Appendix A Technical Specifications Date of Issuance:
Feb. 28, 1973 Amendment No. 206
UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON, 1). C. 20545 Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc.
(Vermont Yankee Nuclear Power Station)
Docket No.
50-271 Facility Operating License License No.
DPR-28 Amendment No.
5 The Atomic Energy Commission (the Commission) having found that:
- a. Construction of the Vermont Yankee Nuclear Power Station (the facility) has been substantially completed in conformity with the application, as amended, the Provisional Construction Permit No.
CPPR-36, the provisions of the Atomic Energy Act of 1954, as amended (the Act),
and the rules and regulations of the Commission as set forth in Title 10, Chapter 1, CFR; and
- b. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; and
- c. There is reasonable assurance (1) that the activities authorized by this amended operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; and
- d. Entergy Nuclear Vermont Yankee, LLC is financially qualified and Entergy Nuclear Operations, Inc. is technically and financially qualified to engage in the activities authorized by this amended operating license, in accordance with the rules and regulations of the Commission; and
- e. Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. have satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements" of the Commission's regulations; and
- f.
The issuance of this amended operating license will not be inimical to the common defense and security or to the health and safety of the public; and Amendment No.
2
- g.
After weighing the environmental, economic, technical and other benefits of the facility against environmental costs and considering available alternatives, the issuance of this amended operating license (subject to the conditions for protection of the environment set forth herein) is in accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirements of said Appendix D have been satisfied.
Accordingly, Facility Operating License No.
DPR-28, as amended, issued to Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc.
is hereby amended in its entirety to read:
- 1. This license applies to the Vermont Yankee Nuclear Power Station (the facility),
a single cycle, boiling water, light water moderated and cooled reactor, and associated electric generating equipment.
The facility is located on Entergy Nuclear Vermont
- Yankee, LLC's site, in the Town of Vernon, Windham County, Vermont, and is described in the application as amended.
- 2.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
A.
Pursuant to Sections 104b of the Atomic Energy Act of 1954, as amended (the Act),
and 10 CFR Part 50, "Licensing of Production and Utilization Facilities,"
Entergy Nuclear Vermont Yankee, LLC to possess and use, and Entergy Nuclear Operations, Inc.,
to possess, use, and operate the facility as a utilization facility at the designated location on the Entergy Nuclear Vermont Yankee, LLC site.
B.
Entergy Nuclear Operations, Inc., pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special
.147 nuclear material as reactor fuel, in accordance with the 2.14.77 limitations for storage and amounts required for reactor operation as described in the Final Safety Analysis Report, as supplemented and amended.
C.
Entergy Nuclear Operations, Inc., pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for calibration of reactor instrumentation and radiation monitoring equipment, and as fission detectors in amounts as required.
D.
Entergy Nuclear Operations, Inc., pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components.
Amendment No.
3 E. Entergy Nuclear Operations, Inc., pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not to separate, such byproduct and special nuclear material as may be produced by operation of the facility.
- 3.
This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A. Maximum Power Level Entergy Nuclear Operations, Inc.
is authorized to operate the facility at reactor core power levels not to exceed 1593 megawatts thermal in accordance with the Technical Specifications (Appendix A) appended hereto.
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment 205, are hereby incorporated in the license.
Entergy Nuclear Operations, Inc. shall operate the facility in accordance with the Technical Specifications.
C.
Reports Entergy Nuclear Operations, Inc. shall make reports in accordance with the requirements of the Technical Specifications.
D.
Records Entergy Nuclear Operations, Inc. shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E.
Environmental Conditions Pursuant to the Initial Decision of the presiding Atomic Safety and Licensing Board issued February 27,
- 1973, the following conditions for the protection of the environment are incorporated herein:
Amendment No.
- 206,
- 1. This paragraph deleted by Amendment No. 206, October 22, 2001.
- 2.
This paragraph deleted by Amendment 131, 10/07/91.
- 3.
This paragraph deleted by Amendment No. 206, October 22, 2001.
- 4.
If harmful effects or evidence of irreversible damage in land or water ecosystems as a result of facility operation are detected by Entergy Nuclear Operations, Inc.'s environmental monitoring program, Entergy Nuclear Operations, Inc. shall provide an analysis of the problem to the Commission and to the advisory group for the Technical Specifications, and Entergy Nuclear Operations, Inc. thereafter will provide, subject to the review by the aforesaid advisory group, a course of action to be taken immediately to alleviate the problem.
- 5.
Entergy Nuclear Operations, Inc. will grant authorized representatives of the Massachusetts Department of Public Health (MDPH) and Metropolitan District Commission (MDC) access to records and charts related to discharge of radioactive materials to the Connecticut River.
- 6.
This paragraph deleted by Amendment No. 206, October 22, 2001.
Amendment No.
- 206, I
- 7.
This paragraph deleted by Amendment No.
206, October 22, 2001.
- 8.
Entergy Nuclear Operations, Inc. will permit authorized representatives of the MDPH and MDC to examine the chemical and radioactivity analyses performed by Entergy Nuclear Operations, Inc.
- 9.
Entergy Nuclear Operations, Inc. shall immediately notify MDPH, or an agency designated by MDPH, in the event concentrations of radioactive materials in liquid effluents, measured at the point of release from the Vermont Yankee
- facility, exceed the limit set forth in the facility Offsite Dose Calculation Manual.
Entergy Nuclear Operations, Inc.
will also notify MDPH in writing within 30 days following the release of radioactive materials in liquid effluents in excess of 10 percent of the limit set forth in the facility Offsite Dose Calculation Manual.
- 10. A report shall be submitted to MDPH and MDC by May 15 of each year of plant operation, specifying the total quantities of radioactive materials released to the Connecticut River during the previous calendar year.
The report shall contain the following information:
(a) Total curie activity discharged other than tritium and dissolved gases.
(b) Total curie alpha activity discharged.
(c) Total curies of tritium discharged.
(d) Total curies of dissolved radio-gases discharged.
(e) Total volume (in gallons) of liquid waste discharged.
Amendment No.
- 296, (f) Total volume (in gallons) of dilution water.
(g) Average concentration at discharge outfall.
(h) This paragraph deleted by Amendment No.
206, October 22, 2001.
(i)
Total radioactivity (in curies) released by nuclide including dissolved radio-gases.
(j)
Percent of the facility Offsite Dose limit for total activity released.
Calculation Manual
- 11. This paragraph deleted by Amendment No.
- 206, October 22, 2001.
- 12.
This paragraph deleted by Amendment No.
206, October 22, 2001.
- 13.
The Entergy Nuclear Operations, Inc. shall establish and maintain a system of emergency notification to the states of Vermont and New Hampshire, and the Commonwealth of Massachusetts, satisfactory to the appropriate public health and public safety officials of those states and the Commonwealth, which provides for:
- a.
Notice of site emergencies as well as general emergencies.
- b.
Direct microwave communication with the state police headquarters of the respective states and the Commonwealth when the transmission facilities of the respective states and the Commonwealth so permit, at the expense of Entergy Nuclear Operations, Inc.
Amendment No.
- 206,
- c.
A verification or coding system for emergency messages between Entergy Nuclear Operations, Inc. and the state police headquarters of the respective states and the Commonwealth.
- 14.
Entergy Nuclear Operations, Inc. shall furnish advance notification to MDPH, or to another Commonwealth agency designated by MDPH, of the time, method and proposed route through the Commonwealth of any shipments of nuclear fuel and wastes to and from the Vermont Yankee facility which will utilize railways or roadways in the Commonwealth.
F. Entergy Nuclear Operations, Inc. shall implement and maintain in effect all provisions of the approved Fire A-168 Protection Program as described in the Final Safety 2/24/99 Analysis Report for the facility and as approved in the SER dated January 13,
- 1978, and supplemental SERs, dated 9/12/79, 2/20/80, 4/15/80, 7/3/80, 10/24/80, 11/10/81, 1/13/83, 7/24/84, 3/25/86, 12/1/86, 12/8/89, 11/29/90, 8/30/95, 3/23/97, 6/9/97, 8/12/97, 3/6/98, 3/31/98, 9/2/98, and 2/24/99, subject to the following provisions:
Entergy Nuclear Operations, Inc. may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
G. Security Plan Entergy Nuclear Operations, Inc. shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to IOCFR73.55 (51FR27817 and 27822) and to the authority of 10CFR50.90 and 10CFR50.54(p).
The plans, which contain Safeguards Information protected under IOCFR73.21, are entitled:
"Vermont Yankee Nuclear Power Station Physical Security Plan," with revisions submitted through March 16, 1988; "Vermont Yankee Nuclear Power Station Training and Qualification Plan," with revisions submitted through November 10, 1982; and "Vermont Yankee Nuclear Power Station Safeguards Contingency Plan," with revisions submitted through December 30, 1985.
Changes made in accordance with IOCFR73.55 shall be implemented in accordance with the schedule set forth therein.
Amendment No.
2-9-6-,
A-107 8/25/88 10/20/88 H.
This paragraph deleted by Amendment No.
107, 8/25/88.
I.
This paragraph deleted by Amendment No.
131, 10/7/91.
- 4.
This license is effective as of the date of issuance and shall expire at midnight on March 21, 2012.
FOR THE ATOMIC ENERGY COMMISSION Original Signed By Roger S.
Boyd /f/
A.
Giambusso, Deputy Director for Reactor Projects Directorate of Licensing
Enclosures:
Appendix A Technical Specifications Date of Issuance:
Feb. 28, 1973 Amendment No.
206 A-127 12/17/90 Attachment B
APPENDIX A TO OPERATING LICENSE DPR-28 TECHNICAL SPECIFICATIONS AND BASES FOR VERMONT YANKEE NUCLEAR POWER STATION
- VERNON, VERMONT DOCKET NO.
50-271 Reissued by Change Nos.
13, 15, and 17 Dated 1/17/74, 1/28/74, and 4/10/74
VYNPS 5.0 DESIGN FEATURES LLC.
5.1 Site The station is located on the property on the west bank of.the Connecticut River in the Town of Vernon, Vermont, which (hIVereont Qanke _N41ear/Poweio Corra tie either owns or to which it has perpetual rights and easements.
The site plan showing the exclusion area boundary, boundary for gaseous effluents, boundary for liquid effluents, as well as areas defined per 10CFR20 as "controlled areas" and "unrestricted areas" are on plant drawing 5920-6245.
The minimum distance to the boundary of the exclusion area as defined in 10CFRI00.3 is 910 feet.
No part of the site shall be sold or leased and no structure shall be located on the site except structures owned byLh7Verm~nt Y~kee*
uc ar Vower Zoporri r or related utility companies and used in conjunction with normal utility operations.
5.2 Reactor A.
The core shall consist of not more than 368 fuel assemblies.
B.
The reactor core shall contain 89 cruciform-shaped control rods.
The control material shall be boron carbide powder (B4C) or hafnium, or a combination of the two.
5.3 Reactor-Vessel The reactor vessel shall be as described in Table 4.2-3 of the FSAR.
The applicable design codes shall be as described in subsection 4.2 of the FSAR.
5.4 Containment A.
The principal design parameters and applicable design codes for the primary containment shall be as given in Table 5.2.1 of the FSAR.
B.
The secondary containment shall be as described in subsection 5.3 of the FSAR and the applicable codes shall be as described in Section 12.0 of the FSAR.
C.
Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in subsection 5.2 of the FSAR.
5.5 Spent and New Fuel Storage A.
The new fuel storage facility shall be such that the effective multiplication factor (Keff) of the fuel when dry is less than 0.90 and when flooded is less than 0.95.
B.
The Keff of the fuel in the spent fuel storage pool shall be less than or equal to 0.95.
C.
Spent fuel storage racks may be moved (only) in accordance with written procedures which ensure that no rack modules are moved over fuel assemblies.
Amendment No. 7ý,
8-,
1-2-,
4-5-,
183 253
APPENDIX A TO OPERATING LICENSE DPR-28 TECHNICAL SPECIFICATIONS AND BASES FOR VERMONT YANKEE NUCLEAR POWER STATION
50-271 Reissued by Change Nos.
13, 15, and 17 Dated 1/17/74, 1/28/74, and 4/10/74 Amendment No.
VYNPS 5.0 DESIGN FEATURES 5.1 Site The station is located on the property on the west bank of the Connecticut River in the Town of Vernon, Vermont, which Entergy Nuclear Vermont Yankee, LLC either owns or to which it has perpetual rights and easements.
The site plan showing the exclusion area boundary, boundary for gaseous effluents, boundary for liquid effluents, as well as areas defined per 10CFR20 as "controlled areas" and "unrestricted areas" are on plant drawing 5920-6245.
The minimum distance to the boundary of the exclusion area as defined in 10CFRI00.3 is 910 feet.
No part of the site shall be sold or leased and no structure shall be located on the site except structures owned by Entergy Nuclear Vermont Yankee, LLC or related utility companies and used in conjunction with normal utility operations.
5.2 Reactor A.
The core shall consist of not more than 368 fuel assemblies.
B.
The reactor core shall contain 89 cruciform-shaped control rods.
The control material shall be boron carbide powder (B4C) or hafnium, or a combination of the two.
5.3 Reactor Vessel The reactor vessel shall be as described in Table 4.2-3 of the FSAR.
The applicable design codes shall be as described in subsection 4.2 of the FSAR.
5.4 Containment A.
The principal design parameters and applicable design codes for the primary containment shall be as given in Table 5.2.1 of the FSAR.
B.
The secondary containment shall be as described in subsection 5.3 of the FSAR and the applicable codes shall be as described in Section 12.0 of the FSAR.
C.
Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with standards set forth in subsection 5.2 of the FSAR.
5.5 Spent and New Fuel Storage A.
The new fuel storage facility shall be such that the effective multiplication factor (Keff) of the fuel when dry is less than 0.90 and when flooded is less than 0.95.
B.
The Keff of the fuel in the spent fuel storage pool shall be less than or equal to 0.95.
C.
Spent fuel storage racks may be moved (only) in accordance with written procedures which ensure that no rack modules are moved over fuel assemblies.
Amendment No.
9-2, -8, 1-2-3, 15 1-,83 2S3