NUREG-1253, License NPF-69.Amend 17 to Indemnity Agreement B-36 & NUREG-1253 Encl
| ML17055D145 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/02/1987 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | Central Hudson Gas & Electric Co, Long Island Lighting Co, New York State Electric & Gas Corp, Niagara Mohawk Power Corp, Rochester Gas & Electric Corp |
| Shared Package | |
| ML17055D146 | List: |
| References | |
| CON-IIT07-462-91, CON-IIT7-462-91 NUREG-1253, NUREG-1455, NUDOCS 8708240055 | |
| Download: ML17055D145 (16) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAMK POWER CORPORATION ROCHESTER GAS AND ELECTRIC CORPORATION CENTRAL HUDSON GAS 8
ELECTRIC CORPORATION NEW YORK STATE ELECTRIC 8
GAS CORPORATION LONG ISLAND LIGHTING COMPANY DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT 2 FACILITY OPERATING LICENSE License No. NPF-69 I.
The Nuclear Regulatory Comission (the COIImission or the NRC) has found that:
A.
The application for a license filed by the Niagara Mohawk Power Corporation, acting on behalf of itself and as aqent for Rochester Gas and Electric Corporation, Central Hudson Gas 8 Electric Corporation, New York State Electric Il Gas Corporation, and Long Island Lighting Company (the licensees)*,
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the ComIission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been du'ly made; B.
Construction of the Nine Mile Point Nuclear Station, Unit 2 (the facility) has been substantially completed in conformity with Construction Permit No.
CPPR-112 and the application, as
- amended, the provisions of the Act, and the regulations of the CoIITIIission; C.
The facility will operate in conformity with the application, as
- amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance in Section 2.D. below);
D.
There is reasonable assurance:
(i) that the activities authorized by this operating license can be conducted without endangering the health
- Niagara Mohawk Power Corporation is authorized to act as agent for the other listed owners and has exclusive responsibility and control over the physical construction, operation, and maintenance of the facility.
8708240055 870702 PDR ADQCK 05000410 P
and safety of the public, and (ii) that such activities will be conducted in compliance with the Comnission's regulations'et forth in IO CFP.
Chapter I (except as exempted from compliance in Section 2.D. below);
E.
Niagara Mohawk Power Corporation is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.
The licensees have satisfied the applicable provisions of 10 CFR Part
- 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No.
NPF-69, subiect to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix 8, is in accordance with 10 CFR Part 51 of the 'Commission's regulations and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct, and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70.
2.
Based on the foregoing findings regarding this facility, and pursuant to.
. approval by the Nuclear Regulatory Commission at a meeting on July I, 1987, Facility Operating License No. NPF-69, which supersedes the license for fuel loading and low power testing, License No. NPF-54, issued on October 31,
- 1986, is hereby issued to the Niagara Mohawk Power Corporation, Rochester Gas and Electric Corporation, Central Hudson Gas 8 Electric Corporation, New York State Electric
& Gas Corporation, and Long Island Lighting Company (the licensees) to read as follows:
A.
This license applies to the Nine Mile Point Nuclear Station, Unit 2, a boiling water nuclear reactor, and associated equipment (the facility) owned by Niagara Mohawk Power Corporation, Rochester Gas and Electric Corporation, Central Hudson Gas
& Electric Corporation, New York State Electric
& Gas Corporation, and Long Island Lighting Company.
The facility is located on the licensees'ite on the southeast shore of Lake Ontario in the town of Scrfba, Oswego County, New York, and is described in the Niagara Mohawk Power Corporation "Final Safety Analysis Report,"
as supplemented and amended, and in the "Environmental Report,"
as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Comnission hereby licenses:
(I)
Niagara Mohawk Power Corporation, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess,
- use, and operate the facility
(2) at the above designated location in Oswego County, New York, in accordance with the procedures and limitations set forth in this license; Rochester Gas and Electric Corporation, Central Hudson Gas 5
Electric Corporation, New York State Electric 5 Gas Corporation, and Long Island Lighting Company, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess the facility at the designa'ted location in Oswego
- County, New York, in accordance with the pro-cedures and limitations set forth in this license:
(3)
(4)
(5)
Niagara Mohawk Power Corporation, 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; Niagara Mohawk Power Corporation, 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 reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; Niagara Mohawk Power Corporation, 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 w'ithout restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
Niagara Mohawk Power Corporation, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Cotnnission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
Maximum Power Level 1
Niagara Mohawk Power Corporation is authorized to operate the facility at reactor core power levels not in excess of 3323 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.
4 (2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, both of which are attached
- hereto, are hereby incorporated into this license.
Niagara Mohawk Power Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
Fuel Stora e and Handlin (Section
- 9. 1, SSER 4
- a ~
b.
Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
h'hen not in the reactor vessel, all fuel assemblies shall be in their shipping containers or storage racks in the New Fuel Vault or in the Spent Fuel Storage Facility except for the following:
i.
No more than three assemblies shall be allowed above the refueling floor.
ii.
No more than one fuel assembly shall be below the refueling floor outside the storage racks.
t c.
The above four fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.
d.
The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time.
(4)
Turbine S stem Maintenance Pro ram (Section 3.5. 1.3. 10, SER Niagara Mohawk Power Corporation shall submit for NRC approval by October 31,
- 1989, a turbine system maintenance program based on the manufacturer's calculations of missile-generation probabilities.
(5)
Inservice Ins ection (Sections 5.2.4.3 and 6.6.3, SSER 5
Niagara Mohawk Power Corporation shall submit an inservice inspection program in accordance with 10 CFR 50.55a(g)(4) for staff review by July 31, 1987.
- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supple-
'ents wherein the license condition is discussed.
(6)
Initial Startu Test Program (Secti on 14,
- SER, SSERs 4 and 5)
Any changes to the Initial Test Program described in Section 14 of the Final Safety Analysis Report made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such chanoe.
(7) 0 eration with Reduced Feedwater Tem erature (Section
- 15. 1, Niagara Mohawk Power Corporation shall not operate the facility with reduced feedwater temperature for the purpose of extending the normal fuel cycle.
The facility shall not be operated with a feedwater heating capacity less than that required to proouce a
feedwater temperature of 400 F at rated steady-state conditions unless analyses supporting such operations are submitted by Niagara Mohawk Powe~ Corporation and approved by the staff.
(8)
Safet Parameter Dis la S stem SPDS Section 18.2 SSERs 3 and 5
Prior to startup following the first refueling outage, Niagara Mohawk Power Corporation shall have operational an SPDS that includes the revisions described in their letter of November 19, 1985.
Before declaring the SPDS operational, the licensee shall complete testing adequate to ensure that no safety concerns exist regarding the operation of the Nine Mile Point Nuclear Station, Unit No.
2 SPDS.
(9)
Detailed Control Room Desi n Review (Section
- 18. 1, SSERs 5 and 6
(a)
Niagara Mohawk Power Corporation shall implement the activ-ities remaining to complete the Detailed Control Room Design Review and correct all human engineering discrepancies (HEDs) in accordance with the schedule and comnitments in letters from C. V. Mangan (NMPC) to E.
G. Adensam (NRC) dated April 14 and June 9, 1986.
(b)
Prior to startup following the first refueling outage, Niagara Mohawk Power Corporation shall provide the results of the reevaluation of normally lit and nuisance alarms for NRC review in accordance with its August 21, 1986 letter.
(c)
Prior to startup following the first refueling outage, Niagara Mohawk Power Corporation shall complete permanent zone banding of meters in accordance with its August 4, 1986 letter.
D.
The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70.
t 1
iii) iv) v)
1 An exemption from the criticality alarm requirements of 10 CFP.
Part 70.24 was granted in the Special Nuclear Materials License No.
SNM-1895 dated Novembe~
27, 1985.
This exemption is described in Section 9.1 of Supplement 4 to the SER.
This previously granted exemption is continued in this operating license.
Exemptions to certain requirements of Appendix J to 10 CFR Part 50 are described in Supplements 3, 4, and 5 to the SER.
These include (a) an exemption from the requirement of Paragraph III,D.2(b)(ii) of Appendix J, exempting overall containment air lock leakage testing unless maintenance has been performed on the air lock (Section 6.2.6 of SSER 5)*; (b) an exemption from the requirement of Paragraph III.C.3 of Appendix J, exempting. main steam isolation valve measured leakage from the combined leakage rate limit of 0.6 La. (Section 6.2.6 of SSER 5); (c) an exemption from Paragraph III of Appendix J, exempting the hydraulic control system for the reactor recirculation flow control valves from Type A and Type C leak testing (Section 6.2.6 of SSER 3); (d) an exemption from Paragraph III.D.3 of Appendix J, exemptinq Type C testing on traversing incore probe system shear valves.
(Section 6.2.6, SSER 4)
An exemption to Appendix A to 10 CFR Part 50 exempting the Control Rod Drive (CRD) hydraulic lines to the reactor recirculation pump seal purge equipment from General Design Criterion (GDC) 55.
The CRD hydraulic lines to the reactor recirculation pump seal purge equipment use two simple check valves for the isolation outside containment (one inside).
(Section 6.2.4, SSER 3)
A schedular exemption to GDC 2, Appendix A to IO CFR Part 50, until the first refueling outage, to demonstrate the adequacy of the.downcomer design under the plant faulted condition.
This exemption permits additional analysis and/or modifications, as necessary, to be completed by the end of the first refueling outage.
(Section 6.2.1.7.4, SSER 3)
A schedular exemption to GDC 50, Appendix A to 10 CFR Part 50 to allow Niagara Mohawk Power Corporation until start-up following the "mini-outage," which is to occur within 12 months of commencing power operation (entering Operational Condition 1), to install redundant fuses in circuits that use transformers for redundant penetration protection in accordance with their letter of August 29, 1986 (NMP2L 0860).
(Section 8.4.2, SSER 5)
- The parenthetical notation following the discussion of each exemption denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the safety evaluation of the exemption is discussed.
Il IJ e
-7" vi)
" A schedular exemption to 10 CFR 50.55a(h) for the Neutron Monitoring System until completion of the first refueling outage to allow'Niagara Mohawk Power Corporation to provide qualified isolation devices for Class 1E/non-lE interfaces described in Niagara Mohawk Power Corporation's letters of June 23, 1987 (NMP2L 1057) and June 25, 1987 (NMP2L 1058).
(Section 7.2.2.10 SSER 6)
For the schedular exemptions in iv), v), and vi), above, Niagara Mohawk Power Corporation, in accprdance with its letter of October 31,
- 1986, shall certify that all systems, components, and modifications have been completed to meet the requirements of the regulations for, which the exemptions have been granted and shall provide a summary description of actions taken to ensure that the regulations have been met.
This certifi-cation and summary shall be provided 10 days prior to the expiration of each exemption period as described above.
The exemptions set forth in this Section 2.D are authorized by law, will not present an undue risk to public health and safety, and are consistent with the, common defense and security.
These exemptions are hereby granted.
The special circumstances regarding each exemption are identified in the referenced section of the Safety Evaluation Report and the supplements thereto.
The exemptions in ii) through vi) are granted pursuant to 10 CFR 50. 12.
Mith these exemptions, the facility will operate to the extent authorized herein, in conformity with the application, as
- amended, the provisions of the Act, and the rules and regulations of the Commission.
E.
Niagara Mohawk Power Corporation shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans, including all amendments and revisions made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
These plans, which contain safe-guards information protected under 10 CFR 73.21, are entitled:
"Nine Mile Point Nuclear Station Unit 2 Physical Security Plan," with revi'sions submitted through April 24, 1987;. "Nine Mile Point Nuclear Station Unit 2 Security Training and gualification Plan," with revisions sub-mitted through January 28, 1985; and "Nine Mile Point Unit 2 Safeguards Contingency Plan" (Chapter 8 of the Security Plan), with revisions submitted through April 24, 1987.
F.
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, Niagara Mohawk Power Corporation shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System, with written followup within 30 days in accord-ance with the procedures described in 10 CFR 50.73(b), (c), and (e).
G.
Niagara Mohawk Power Corporation shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility through Amendment No.
27 and as described in submittals dated March 25, May 7 and 9, June 10 and 25, July 11 and 16, August 19 and 22, September 5, 12, and 23, October 10, 21, and 22, and December 9, 1986, and April 10 and May 20,
- 1987, and as approved in the SER dated February 1985 !and Supplements 1 throuoh 6) subject to the following provision:
Niagara Mohawk Power Corporation 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.
H.
The licensees shall have and maintain financial protection of such type and in such amounts as the Coomission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as
- amended, to cover public liability claims.
I.
This license is effective as of the date of issuance and shall expire at midnight on October 31, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosures:
1.
Appendix A - Technical Specifications (NUREG-1253) 2.
Appendix 8 - Environmental Protection Plan Thomas E. Murley, Director Office of Nuclear Reactor Regulation Date of Issuance:
July 2, 1987
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