ML20042F078
| ML20042F078 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point, Indian Point, Ginna, FitzPatrick, 05000054, Shoreham |
| Issue date: | 04/25/1990 |
| From: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | Boehlert S HOUSE OF REP. |
| Shared Package | |
| ML20042F079 | List: |
| References | |
| NUDOCS 9005070194 | |
| Download: ML20042F078 (4) | |
Text
~
L i
et a
April 25,1990 s
l The Honorable Sherwood Boehlert United States House of Representatives j
Washington, D.C.
20515
Dear Congressman Boehlert:
I am responding to your letter dated March 29, 1990, that forwarded a request made by Ms. Cindy Monaco of Cortland County for copies of the.foll mie (1) the licenses for all of the nuclear power plants Iccatd in documents:
New York State, and (2) amendments to the licenses that would extend the operating lives of these plants.
Pursuant to telephone conversations on_ March 30, 1990, between Ms. Monaco, Mr. Thom Heckard of your staff, and Mr. Mike Callahan of the U.S. Nuclear Regulatory Commission, Ms. Monaco changed the information requested in item (1) to include.the following information for all nuclear power plants located within New York State and for the Cintichem, Inc., reactor:
- Date the construction permit was issued
- Date the operating license was issued
- Date of first commerical operation
- Date the license expires
(
Enclosed is our response to-the information requested, as modified by Ms. Monaco.
I trust that this information will be resronsive to Ms. Monaco's request.
- d}.incerely, 06%B3\\IIE"MJamesM. Taylor i
names 3.Ta j;
Executive Director for Operations
Enclosures:
1.
Reactor Licensing Information 2.
License Amendment for FitzPatrick 3.
License Amendment for Indian Point 2 DISTRIBUTION:
- w/cy of incoming Central File SVarga OGC DCrutchfield NRC PDR*
BBoger GPA/CA FGillespie E00 #5320 JLinville, RI JTaylor D0udinot*
ED0 Rdg RCapra JPartlow DMossburg EDO #5320*
TMurley/FMiraglia TMartin, RI Bev Clayton PDI-1 Rdg*
WRussell PDI-1 GT File
- DOCUMENT NAME: GT 5320 4
- See previous concurrences PDI-1 PDI-1 Tech Ed PDI-1 AD/RI DRP/DIR ADP:NRR CVogan D0udinot:rse RCapra BBoger SVarga JPartlow 4/ /90 4/
/90 4/ /90 4/
/90 4/
/90 4/
/90 4/
/90 NRR:D GPA A TMurley
- T or 24h9 W
\\
kr,A
- ermutsgr g
j n
l
\\
ENCLOSURE 1 LICENSING INFORMATION ON COMMERCIAL NUCLEAR POWER REACTORS AND THE CINTICHEM, INC., REACTOR IN NEW YORK STATE CONSTRUCTION OPERATING FIRST LICENSE PERMIT LICENSING COMMERCIAL EXPIRES ISSUED ISSUED OPERATION FITZPATRICK 05/20/70 10/17/74 07/28/75 10/17/2014 GINNA 04/25/66 09/19/69*
07/01/70 04/25/2006 12/10/84**
INDIAN POINT 2 10/14/66 09/28/73 08/01/74 09/28/2013 INDIAN POINT 3 08/13/69 04/05/76 08/30/76 08/13/2009 NINE MILE POINT 1 04/12/65 08/22/69*
12/01/69 04/11/2005 12/26/74**
NINE MILE POINT 2 06/24/74 10/31/86***
03/11/88 10/31/2026 07/02/87****
SHOREHAM 04/14/73 04/21/89 04/13/2013 CINTICHEM INC.
REACTOR 10/31/57 09/07/61 03/03/62 06/30/2000 Provisional Operating License Issued Full Term Operating License Issued Low Power Operating License Issued (restricted to 5% of rated power)
NN Full Power Operating Licensing Issued NOTES Applications to extend the expiration dates of the Ginna and Nine Mile Point Unit 1 operating licenses to 40 years from the date of issuance of the full-power license were submitted to the NRC on October 5, 1989, and July 27, 1988, respectively, and are currently being reviewed.
Amendments extending the expiration dates of the operating licenses to 40 years from the date of issuance of the full-power license for the James A. FitzPatrick and the Indian Point Unit 2 plants were issued on July 10, 1989, and April 21, 1987, respectively (copies attached),
The licensee for Indiar Point Unit 3 is scheduled to submit to the RRC in 1990 an amendment to extend the expiration date of its operating license to 40 years from the date of issuance of the full-power license.
The operating license that was issued on September 7, 1961, to Cintichem, Inc.,
expired in 1981. The license was renewed on September 28, 1984
...... ~.
z km[40p
(
UNITED STATES
. NUCLEAR REGULATORY COMMISSION '
a
- s' l
C wAssiwoTow, p. c. rosas
'.,\\,,,,,
' July 10.- 1989 Docket No. 50-333 L
Mr.' John C. Brons l-Executive Vice President - Nuclear Generation i
Power: Authority of the State of New York 123 Main. Street
' White Plains, New. York 10601
Dear Mr. Brons:
SUBJECT:
" ISSUANCE OF AMENDMENT (TAC NO. 66123)
The Commission has issued the enclosed Amendment No.133 n to' Facility Operating License'No.-DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the operating license in' response to your application transmitted by letter dated August 19, 1987.
The amendment extends the expiration date of the operating' license from.
May 20 -2010 to October 17, 2014.
A copy of the related Safety Evaluation is enclosed. 'A Notice of Issuance will l
be included in the Commission's~ next regular bi_-weekly Federal Register notice.
Sincerely,-
l 4
David E. LaBarge, Project Manager.
Project Directorate I-1 Division of Reactor Projects,.I/II
Enclosures:
1.
Amendment No.133 to DPR 2.
Safety Evaluation-cc: w/ enclosures See next page i
'i k
-. _ y
't
.,t.**
, Mr 0 John.Co Brons
. James A. FitzPatrick Nuclear' i
P6wer Authority of the State of _New York '
Power Plant a
cc:
Mr. Gerald C. Goldstein Ms. Donna Ross 3'
Assistant General Counsel New York State Energy Office i-Power Authority of the State 2 Empire-State Plara-n of New York--
16th Floor 1
10 Columbus Circle Albany, New York 12223 t
f Resident Inspector's Office Regional Aeninistrator, Region 1 4
l U. S. Nuclear Regulatory Comission U. S. Nuclear Regulatory Comission 2
Post Office Box 136 475 Allendale Road Lycoming, New York 13093 King of; Prussia, Pennsylvania 19406
[
I i
Mr. William Fernander Mr. A.-Klausman F
' Resident Manager Senior Vice President - Appraisal l
James A. FitzPatrick Nuclear and Compliance Services Power Plant Power Authority of the State Post Office Box 41 of New York l
Lycoming, New York 13093 10 Columbus Circle
Mr. J. A. Gray, Jr.
Mr. George W11verding, Manager i
Director Nuclear Licensing - RWR Nuclear Safety Evaluation Power Authority of the State Power Authority of the State-l of New York of New York-1 123 Main Street 123 Main Street
{
White Plains, New York 10601 White Plaints, New York 10601 l
Mr. Robert P. Jones, Supervisor Mr. R. E. 9eedle Town of Scriba Vice President Nuclear Support R. D. #4 Power Authority of the State Oswego, New York 13126 of New York
.123 Main Street Mr. J. P. Payne, President Power Authority of the State of New York Mr. S'.-S. Zulla.
i 10 Columbus Circle 3
Vice President Nuclear Engineering i
New York, New York 10019 Power Authority of the State of New York j'
123 Main. Street Mr. Richard Patch White Plains, New York 10601 Quality Assurance Superintendent James-A. FitzPatrick Nuclear Power Plant Post Office Box 41 Vice President Nuclear Operations
'Lycoming, New York 13093 Power Authority of the State of New York 123 Main Street
~
Charlie Donaldson, Esquire White Plains, New York 10601 Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 L
.,. g' tick'
-E
+
o UNITED STATES g -
NUCLEAR REGULATORY COMMISSION i [E-cj WASHINGTON D. C. 20666
./
POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 i
JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMEN 0 MENT-TO FACILITY OPERATING LICENSE-Amendment No. 133 License No..DPR-59 1.
The Nuclear Regulatory Comission'(the Comission) has found that:
A.
The application for amendment by Power Authority of the State ~
of New York (the licensee) dated August 19, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter-I; i
i B.
The facility will operate in conformity with the application, i
the provisions'of the Act, and the -rules and regulations of j
the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance.with the Commission's regulations;
.j D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements 3
have been satisfied, t
2.
Accordingly, Facility Operating License No. DPR-59 is hereby amended to j
read as follows:'
1 k
]
{
v q
-h'07 hk a
2 A.
Change paragraph 2.F. to read as follows:
This amended license is effective at 11:59 p.m., EDST, June 4,1977, and shall expire at midnight October 17, 2014, 3.
This license amendment is effective as of the date of its issuance to be impleatnted within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION T M a..C p Robert A. Capra, Director Project Directorate 1 1 Division of Reactor Projects, I/!!
Date of Issuance: July 10, 1989 1
-~ - -
. po 5 tog'o, UNITED STATES NUCLEAR REGULATORY COMMISSION e
5
\\,...../)
W A6HINGTON, D. C. 20666 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.131 TO FACILITY OPERATING LICENSE N0. OPR 59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT pQtKETNO.50-333 E-INTRODUCTION By letter dated August 19, 1987, the Power Authority of the State of New York (PASNY or the licensee) requested an amendment to the Facility Operating License DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The proposed M
1 amendment would extend the expiration date for the license from May 20, 2010 to 1
October 17, 2014 01SCUS$10N Title 10 CFR 50.51 specifies that each license will be issued for a fixed period of time not to exceed 40 years from the date of issuance. The currently licensed term for the FitzPatrick plant is 40 years, comencing with the issuance of the construction permit on May 20, 1970.
However, since the license expiration date is May 20, 2010, if the construction time is taken into account, this represents an effective operating license term of about 35.5 years from the date of issuance of the operating license (October 17, 1974). Consistent with Section 50.51 of the Comission's regulations, the licensee has requested an extension of the operating license so that the fixed period of the license would end 40 years after the date of issuance of the operating license.
EVALVATION The NRC staff has evaluated the safety issues associated with issuance of the proposed licer.se amendment which would allow approximately four and one-half additional years of plant operation. The issues addressed consist of additional radiation exposure to the licensee's operating staff, impacts on the off-site-population, and the general aging of plant structures and equipment. The impact of additional radiation exposure to the facility o>erating staff and the impact on the general population in the vicinity of tie FitzPatrick nuclear plant are addressed in the NRC staff's Environmental Assessment dated April 27, 1989.
The components of the reactor coolant pressure boundary were designed, built and tested to ANSI B31.1.0 (1967) and the appropriate ASME Boiler and Pressure Vessel Codes, Regulatory standards, and ' supplemental criteria in compliance V7 NY
2 with the requirements of 10 CFR Part 50 Section 50.55a " Codes and Standards."
The initial inservice inspection program, was described in the FSAR and Technical Specifications and comply with the requirements of 10 CFR 50.55a(g). Upon completion of the first ten year inspection interval on July 28,1985, the licensee evaluated the inservice inspection program and implemented enhancements. Also, by letter dated September 30, 1985, the licensee submitted a revision to the program for the second ten-year interval as required by 10 CFR 50.55a(g) and submitted relief reouests by letter dated August 6,lly, the licensee is evaluating the inservice testing program inBoth of th 1987.
Additiona accordance with Generic Letter 89-04, " Guidance on Developing Acceptable Inservice Testing Programs," dated April 3, 1989. Therefore, the program is either current or provisions are in place which will address or identify any concerns. Present Inservice Inspection is done in accordance with ASME Section XI 1980 Edition through Summer of 1981 Addenda.
Inspections conducted at several boiling (water reactors (BWRs) indicated intergranular stress corrosion cracking IGSCC) in large-diameter stainless steel pipe. Since the NRC staff considered this a generic problem, the Commission issued Generic Letter 84-11 which required a reinspection program at all BWRs. This program involved welds in stainless steel pipes greater than four inches in diameter, in systems that are part of or connected to the reactor coolant pressare boundary, out to the second isolation valve.
If IGSCC was discovered, repair, analysis and additional surveillance were required to ensure the continued integrity of the affected pipe.
Generic Letter 88 01, issued on January 25, 1988, superseded Generic letter 84-11, and included a copy of NUREG-0313 Revision 2 " Technical Report on Material Selection and Processing Guide 1Ines for BWR Coolant Pressure Boundary Piping." NUREG-0313, Revision 2, describes methods acceptable to the staff to control the susceptibility of BWR ASME Boiler and Pressure Vessel Code Class 1, 2, and 3 pressure boundary pipino and safe ends to intergranular stress corrosion cracking. The revision describes the technical bases for the staff's positions on the following items: materials of construction; processes to minimize or control IGSCC; water chemistry; reinforcement by weld overlay; replacement of piping; stress improvements; clamping devices; crack characterization and repair criteria; inspection methods, schedules, and personnel; and limits on number of cracked weldments in piping.
For piping that does not conform to the staff positions, varying degrees of inservice inspection are required to ensure structural integrit of the boundary piping system, pursuant to paragraph 50.55a(y)(6)(ii) pressure g
of 10 CFR Part 50 By letter dated August 16, 1988, and supported by letter dated August 19, 1988, and others, the licensee responded to Generic Letter 88 01. describing the licensee's plans and program for implementation of the NRC staff's positions specified in the generic letter. The licensee response still is
a
. under review. However, the staff will ensure that the licensee's program meets the staff requirements.
In their responses to Generic Letter 88-01, the licensee has outlined a comprehensive and a ressive IGSCC detection and mitigation program.
This program includes:
)inspectionofsusceptiblewelds;(2)InductionHeating Stressimprovement(IHSI)ofweldsintheReactorRecirculationandthe Residual Heat Pemoval Systems applied during two maintenance outages in 1984 and Resistance Heating Stress Improvement (RHST) applied to two Reactor Recirculation System welds during-the 1987 refueling outage; (3) planned selective replacement or removal of piping such as the RHR suction piping and Reactor Water Cleanup suction piping which were replaced and the Reactor Recirculation S outage; and (4)ystem bypass lines which were removed during the 1987 refueling hydrogen water chemistry and crack arrest verification system.
This program as well as application of weld overlays when IGSCC is detected and other req,uirements of NUREG-0313, have been incorporated to address the IGSCC concerns rather than replacement of the austentic stainless steel piping.
From our evaluation we conclude that compliance with the codes, standards, and regulatory requirements to which the mechanical equipment for thG FitzPatrick Plant was originally analyzed, constructed, tested and inspected, including the inservice inspection programs being in compliance with Section XI of the ASME Boiler and Pressure Yessel Code and the other augmented-inspections of austenitic stainless steel piping, provide adequate assurance that the structural integrity of components important to safety will be maintained during the additional periods authorized by this amendment.
Any significant degradation by an active mechanism would be discovered and the mechanical equipment or component restored to an acceptable condition.
Therefore, the age of the mechanical ecuipment or component sheeld not be a consideration in the extension of the operating license.
The design and construction of structures and supports was in accordance with various codes and standards applicable at the time of plant construction.
The design bases, fabrication, construction and quality assurance criteria for theplantwerereviewedbytheNRCstaffandpresentedintheSafety Evaluation Report for the James A. FitzPatrick Nuclear Power Plant dated November 20, 1972.
Industrial experience with such structures and supports confirms that a service life in excess of 40 years can be anticipated.
Support structures were constructed to the requirements of Section III of the ASME Boiler and Pressure Vessel Code. Section 9.3 of the staff's SER states that the Class I structures and equipment were designed and aralyzed in accordance with ACI 318-63 code allowable values for reinforced concrete and the AISC code allowable values for structural steel.
The use of the indicated codes, standards, and specifications in the design, analyses, and construction; Appendix B of 10 CFR Part 50 for quality i
I,,-
% assurance; and the identified testing and inservice surveillance requirements; provide reasonable assurance that the concrete and steel structures would withstand continued service for an extended period of at least four and one-half years without impairment of structural integrity.
The Fioal Safety Analysis Report (FSAR) states that the reactor vessel was designed and fabricated for a service life of 40 years, based on the specified design and operating conditions. The vessel was designed, fabricated and inspected in accordance with the requirements of Section !!! of the 1965 ASME Boiler and Pressure Code edition, winter 1966 addehde, and the applicable interpretations and Code Cases for a Class A vessel. Operating limitations on temperature and pressure were established using Section !!! of the ASME Boiler and Pressure Vessel Code and Appendix G of 10 CFR Part 50.
The integrity and performance capability of the ferritic materials in the reactor vessel is assured because the fracture toughness is monitored with a surveillance program in conformance, to the extent practical,l Materials with the recommendations of Appendix H,10 CFR Part 50 " Reactor Vesse Surveillance Program Requirements." TheferrIticmaterialsmustmeetthe fracture toughness properties of Section !!! of the ASME Boiler and Pressure Vessel Code and Appendix G,10 CFR Part 50, " Fracture Toughness Properties."
In accordance with the reactor vessel material surveillance test program, specimens of the vessel base metal the weld heat affected zone metal, and the weldmetalfromareactorsteeljolntwhichsimulatesaweldedjointinthe reactor vessel, along with neutron monitor wires, were placed in capsules near the core mid-height prior to initial reactor startup. They were placed on the reactor vessel wall where neutron exposure is similar to that of the vessel wall. Selected groups of specimens are removed at intervals over the lifetime of the reactor and tested to compare mechanical properties with the properties of control specimens which are not irradiated.
The first surveillance capsule was removed from the reactor vessel in 1985 during the Reload 6/ cycle 7 refueling outage, which corresponds to 5.98 effective full power years. The analysis of the surveillance capsule was reported in General Electric Company Report MDE-49-0386 and submitted to the
(
NRC by the licensee by letter dated April 30, 1986.
The analysis of the surveillance capsule projected the end of life adjusted reference temperature of the limiting beltline material to be 104'F. Also the upper shelf energy for plate and weld material were determined to be 58 ft-lb transverse and 72 ft Ib, respectively.
Paragraph IV. B of Appendix G,10 CFR Part 50 requires that the reactor vessel beltline materials maintain an end-of-life upper shelf energy of no less than 50 ft-lbs and the predicted adjusted reference temperature must not exceed 200'F.
Therefore, the projected 3
I
j I
l I i
fracture toughness properties for the reactor vessel are within the limits set by Appendix G.
l Another temperature limitation in the older boiling water reactors pertains to feedwater nozzles, which are prone to cracking.
In the 1970's, the feedwater nozzles in BWR plants were found to have crac cs due to feedwater leaking i
through the thermal sleeve and sparger.
The nozzle cracking problem has since been resolved. Nevertheless, a pressure-temperature limit has been incorporated into the TS for heatup, cooldown, and critical operation to i
eliminate future cracking.
I Section 50.55a(g) of 10 CFR Part 50, which incorporatesSection XI of the ASME I
Boiler and Pressure Yessel Code, addresses the ongoing inservice inspection and testing requirements for ASME Code Class 1, Class 2 and Class 3 i
components pumps and valves. The license has described their current inserviceInspectionandtestingprogramforweldsandsupportsinasubmittal I
dated July 28, 1985, and for pumps and valves in a submittal dated November 15, 1985. The program details are still under NRC review. However, the current program meets the staff's requirements and the staff will ensure that any issues generated as a result of the present review are properly resolved.
j We conclude that there are no special considerations regarding reactor l
vessel, pump or valve degradation due to the proposed operating lifetime 4
4 1
extension. The structural integrity of the reactor vessel is assured because it was originally designed assuming a 40-year lifetime; it is monitored, inspected, and tested to detect degradation processes at an early stage of development; and it is operated with procedures to assure that design conditions 1
are not exceed 6d. Additionally, the testing program for pumps and valves will enable early detection of degredation which could affect operability of the component.
j The NRC staff concluded in the Environmental Assessment that the annual radiological effects during the additional years of operation that would be authorized by the proposed license amendments are not more than were previously estimated in the Final Environmental Statements, and are acceptable.
The staff ecncludes from its considerations of the design, operation, testing and monitoring of the mechanical equipment, structures, and the reactor vessels that an extension of the operating licenses for the Fit Patrick Nuclear Power Plant to a 40-year service life is consistent with the FSAR, SER, and' i
l submittals made by the licensee, and that there is reasonable assurance that the plant will be able to continue to operate safely for the additional period authorized by this amendment. We also conclude that the plant is operated in i
compliance with the Comission's regulations, and issues associated with plant degradation have been adequately addressed.
In sumary, we find that extension of the operating license for the i
Fit: Patrick Nuclear Power Plant to allow 40-year service life is consistent j
with the Final Environmental Statement and Safety Evaluation Report for the plant and that the Comission's previous findings are not changed.
I n.
- -.. ~
.,n.-
n
i 6-
[NVIRONMENTAL CONSIDERATION A Notice of issuance of Environmental Assessment and Finding of No Significant Impact relating to the sreposed extension of the Facility Operating License termination dates for tae Fit 2 Patrick Nuclear Power Plant was published in the i
Federal Register on May 4, 1989 (54 FR 19265).
1 CONCLUSION j
The Commission made a proposed determination that the amendment involves no significant hazards consideration which was published in the Federal Re11 ster on November 18,1987 (52 FR 44247) with a correction pub 11she6 on Decem>er 28, 1987 (52 FR 48891) and consulted with the State of New York.
No public commentswerereceIved,andtheStateofNewYorkhadnocomments.
We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, and (2) public such activities will be conducted in compliance with the Commission's regulations and the issuance of the amendment will not be inimical to the common defense, and security or to the health and safety of the public.
t Dated: July 10, 1989 PRINCIPALCONTRI}VTOR$:
D. E. LaBarge L. P. Crocker l
l l
}
i 4
9 m
y e
e-~-
3...
p***og t
+p jo, UNITED sTATts NUCLE AR REGULATORY COMMISSION
-i f
nAsmwotow.o c.tosss
(.
p April 21, 1987 j
Docket No. 50 247 Mr. Murray Selman Vice President. Nuclear Power Consolidated Edison Company i
of New York, Inc.
Broadway and Bleakley Avenue New York New York 10511
Dear Mr. Selman:
i The Comission has issueo the enclosed Amendment No.118 to Facility Operating License No. DPR-26 for the Indian Point Nuclear Generating Unit No. 2 The amendment consists of changes to the Technical Specifications in response to your application transmitted by letter dated December 24. 1985, as supplemented December 31, 1966.
January 27,1987 and March 3.1987.
The amendment changes the expiration date for Facility Operating License DPR 26 from October 14, 2006 to September 28, 2013.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Comission's next regular bi-weekly Federal Register notice.
Sincerely, k,' b-
Marylee M. Slosson, Project Manager Project Directorate I-1 Division of Reactor Project's.1/11
Enclosures:
1.
Amendment No.118 to DPR-26 2.
Safety Evaluation ec: w/ enclosures See next page 4
Pr. Purrav Selman Indian Point Nuclear Generating Consolidn'ted Edison Company Station 1/2 of New York, Inc.
CC:
Pavor, Villace of Buchanan Director, Technical Develooment 236 Tate Avenue Programs Buchanan, New York 10511 State of New York Energy Office Agency Building 2 Mr. Jay Dunkleberger Empire State Plaza Office of Policy Analysis Albany, New York 122?3 and Planning York State Energy Office Mr. Peter Kokolakis, Director Building 2, Empire State Plaza Nuclear Licensir,g Albany, New York 12223 New York Power Authority 123 Main Street Robert L. Sprina White Plains, New York 10601 Manager of Rec (uistory Affairs Consolidated dison Company of New York, Inc.
Mr. Walter Stein Broadway and Bleakley Avenue Secretary - NFSC Buchanan, New York 10511 Consolidated Edison Company of New York, Inc.
Senior Pesident Inspector 4 Irving Place - 1822 U.S. Nuclear Regulatory Commission New York, New York 10003 Post Office Box 38 Buchanan, New York 10511 Ezra_1. Bialik Assistant Attorney General Environmental Protection Bureau i
Brent L. Brandenburg New York State Department of Law Assistant General Counsel 2 World Trade Center Consolidated Edison Company New York, New York 10047 of New York, Inc.
4 trying Place - 1822 New York, New York 10003 i
Recional Administrator, Region I U.S. Nuq1 ear Reaulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Carl R. D'Alvia, Escuire Attorney for the Village of Buchanan, New York 305 South Riverside Avenue Croton-on Hudson, New York 10520 4
, ff'go ose,$\\,
UNITE D STATES y
3%y n NUCLE AR REGULATORY COMMISSION
'4 W ASHING TON, D. C. 20666
's, *.... $
CONSOLIDATED EDISION COMPANY OF NEW YORK. INC.
DOCKET NO. 50 247 INDIAN POINT NUCLEAR GENERATING UNIT NO 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.11B License No. DPR-26 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendnent by Consolidated Edison Company of New York Inc. (the licensee) dated December 27, 1985 as supplemented December 31, 1986 and January 27, 1987 complies with the standartis and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the beelth and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, paragraph 3 of Facility Operating License No. OPR-26 is amended to read as follows:
"3.
This license is effective'as of the date of issuance, and shall expire at midnight on September 28, 2013."
.g.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR RECULATORY COMMIS$10N Y & Q.0Mx_)
I Robert A. Capra, Acting Director Project Directorate 1-1 Division of Reactor Projects. 1/II Date of Issuance:
April 21. 1987
. - _.. -., _.. _,...,,.............. = = = =
4
, /,$c,. ;,,
UNITED STATES h
NUCLEAR REGULATORY COMMISSION g
v wasmwotoN, c. c.rosos
~
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.118,TO FACILITY OPERATING LICENSE NO. OPR 26 CONSOLIDATED EDISON COMPANY OF NEW YORK, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247 INTRODUCTION By application dated December 27, 1985, as suoplemented by letters dated December 31, 1986 January 27, 1987 and March 3,1987 Consolidated Edison Company (the licensee) requested an amendment to Facility Operating License No. DPR-26 for Indian Point Nuclear Generating Unit No. 2.
The preoosed amendment would change the license expiration date from October 14, 2006 to September 28, 2013.
The letters dated December 31, 1986, January 27,,1987 and March 3, 1987 were supplementary in nature and in no way changed the' meaning or the content of the December 27, 1985 application.
DISCUS $10N AND EVALUATION Section 103.c of the Atomic Energy Act of 1954 provides that a license is to be issued for a specified period not exceeding 40 years.
10 CFR 50.51 specifies that each license will be issued for a fixed period of time not to exceed 40 years from date of issuance.
10 CFR 50.56 and 10 CFR 50.57 allow the issuance of an operating license pursuant to 10 CFR 50.51 after the construction of the facility has been substantially completed, in confomity with the construction pemit and when other provisions specified in 10 CFR 50.57 are met. The currently licensed tem for the Indian Point Unit No. 2 is 40 years connencing with the issuance of the construction pemits (October 14, 1968). Accounting for the time that was required for plant construction, this represents an effective operating license tem of 33 years for Unit 2.
Consistent with Section 103.c of the Atomic Energy Act and Sections 50.51, 50.57 of the Commission's regulations, the licensee, by its aop11 cation of December 26, 1985, seeks extensions of the operating license terms for Indian Point Unit 2 such that the fixed period of the licenses would be 40 years from the date of operating license issuance.
The licensee's request for extension of the operating license is based on the fact that a 40-year service life was considered during the design and construction of the olant. Although this does not mean that some components will not wear out during the plant lifetime, design features were incorporated which maximize the inspectability of structures, systems and equipment.
4 Co9tfz=+p ' W
, Based upon the above, it is concluded that extension of the operating license for Indian Point Unit No. 2 to allow a 40-year service life is consistent with the safety analysis in that all issues associated with plant aging have already been addressed. Accordingly, we find the oroposed change to the expiration date of the Indian Point Unit No. 2 Facility Operating License to be acceptable.
ENVIRONMENTAL CONSIDERATION A Notice of Issuance of an Environmental Assessrent and Finding of No Significant impact relating to the proposed extension of facility operating license termination date for the Indian Point Unit No. 2 was published in the Federal Register on April 9,1987 (52 FR 11577).
CONCLUSION We have concluded, based on the considerations discussed above, that (1)'there is a reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendments will not be inimical to the connon defense and security or to the health and safety of the public.
Date: April 21, 1987 Principal Contributert M. Slosson L. Lois s
OO'
., 3 4
The Honorable Sherwood Boehlert United States House of Representatives
/
Washington, D.C.
20515
Dear Congressman Boehlert:
I am responding to your letter dated March 29, 1990 hat forwarded a request made by Ms. Cindy Monaco of Cortland County for ies of the following documents: (1) the licenses for all of the nu ar power plants located in New York State, and (2) amendments to the 1 enses that would extend the operating lives of these plants.
Pursuant to telephone conversations afi March 30, 1990, between Ms. Monaco, Mr. Thom Heckard of your staff.
'Mr. Mike Callahan of the U.S. Nuclear Regulatory Comission Ms. Mon changed the information requested in item (1) to include the following infoymation for all nuclear power plants located within New York State and for the Cintichem. Inc., reactor:
- Date the constru n permit was issued
- Date the operating license was issued
- Date of firs Vcommerical operation
- Date the 1 (ense expires Enclosed is ou response to the information requested, as modified by Ms. Monaco, trust that this inforration will be responsive to Ms. Monaco's request.
/
Sincerely.
t Jape [E.T
(
lor Ex ive-Director
Enclosures:
1.
Reactor Licensing Information 2.
License Amendment for FitzPatrick 3.
License Amendment for Indian Point 2 DISTRIBUTION:
- w/cy of incoming CentraT File svarga OGC DCrutchfield NRC PDR*
BBoger GPA/CA FGillespie EDO #5320 JLinville, RI JTaylor 00udinot*
EDO Rdg RCapra JPartlow DMossburg EDO #5320*
TMurley/FMiraglia TMartin. R1 Bev Clayton PDI-1 Rdg*
EDO r/f k
g, q, g WRussell PDI-1 GT File
- DOCUMENT NAME: GT 5320 hg woe oe
- me-h PD1-1 p PDI-1 Roc.c.c Tech Ed PDI-1 1
R ADP:NR1 CVoga D0udinot:rse
- "'" * ** RC a p r a 4/$/90 4/ra /90 4/o./90 4/n2./90 4 0.
Va a JPartlow
/90 4/g /90 e
J r
t
~
A 4 q.7s.
a i
[
9 Q9]fl o,
UNITED STATES h
[3
<g jj.gg g] jig l)d,y's NUCLEAR REGULATORY COMMISSION 4
wAswiwotow. p. c. rosss g
%,....+,/
EDO Principal Correspondence Control 0
FROM:
DUE: 04/4$790 EDO CONTROL: 0005320 000 DT: 03/29/90 FINAL REPLY:
RCp. Sherwood Boehlert TO:
Tom-Combs, CA FOR SIGNATURE OF:
- GRN CRC NO: 90-0327 Exncutive Director DESC:
ROUTING:
ENCLOSES LETTER FROM CINDY MONACO, CORTLAND COUNTY Murley, NRR PLANNING DEPARTMENT REQUESTING INFORNATION CONCERNING NEW YORK STATE'S POWER PLANTS DATE: 04/03/90 ggg/p ASSIGNED TO: C CONTACT:
~.
SPECIAt. INSTRUCTIONS D EMARKst %..
NRR RECEIVED:
april 6, 1990 a: ACTION:WW "DRPR:VARGA ',>
NRR JOUTING: MURLEY/MIRAGLIA PARTLOW RUSSELL CRUTCHFIELD GILLESPIE MOSSBURG ACTION DUE TO NRR DIRECiuk 3 <
BY 9 /d' 94---
- - k.
i
<j I
a