ML17058B422
| ML17058B422 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/26/1974 |
| From: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML17056C371 | List:
|
| References | |
| CON-IIT07-461-91, CON-IIT7-461-91 NUREG-1455, NUDOCS 9305050110 | |
| Download: ML17058B422 (14) | |
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ATOMIC~RGY COMMISSION NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 FACILITY OPERATING LICENSE License No. DPR-63 1.
The Atomic Energy Commission (the Commission) has found that:
A.
The application for license, as amended, filed by the Niagara Mohawk Power Corporation (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made; B.
Construction of the Nine Mile Point Nuclear Station Unit No.
1 has been substantially completed in conformity with Construction Permit No.
CPPR-16 and the application, as
- amended, the provisions of the Act and the rules and regulations of the Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; D.
There is reasonable assurance:
(i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance wi'th the rules and regulations of the Commission; E.
The licensee is technically and financially qualified to engage in the activities authorized by this operating license in accordance with the rules and regulations of the Commission; F.
The licensee has 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 full-term operating license will not be inimical to the common defense and security or to the health and safety of the public; 9305050110 911031 PDR
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'ig(e ( ~r ') 4? 5 .LCiXJ '<."ti r "-'Qd8 <<oh e'. ) () " >> 'r0 8'.'r e) ' a r f. i.,!, i)g'g Ci4 r ",fr', ~">tfurr'<r g'!;, 8 ~r <<'.)r ~~n t,.y .~ ' r '-'O.") Q S > t ~, ~ '5. I,tfr'r:; ~ f c'e+ ~ "~ J by J J J ~~CEl USE Au i I ~ ~, ~~ y q>><<pupa 0g 't,'0t ~<'g~ilOIIL 8. Aftex'eighing the environmental, economic, technical, and other benefits of the f~~p against environmental end other costs and considering available alternatives, the issuance of the full-term Facility'Operating License No. DPR-63 (sub)ect to the conditions for protection of the environment set forth herein) is in accordance vith Appendix D, 10 CFR Part 50 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 villbe in accordance with the Commisaion's regulations in. 10 CFR Parts 30, 40 and 70 including Sections 30.33, 40.32, 70.23 and 70.31. 2. Facility Operating License No. DPR-63 is hereby issued to the Niagara Mohawk Power Corporation to read as folly:s: A. This license applies to the Nine Mile Point Nuclear Station Unit No. 1, a single cycle, forced circulation, boiling light water reactor, and associated equipment (the facility), owned by the Niagara Mohawk Power Corporation, The facility is located on the Nine Mile Point site on the southeast shore of Lake Ontario in Oswego County, New York and is described in the "Final Safety Analysis Report" (with its Amendments Nos. 3 through 13 and its Supplements Nos. 1 through 10) and the ".Environmental Report" (with its Supplements Nos. 1 through 3). B. Subject to the conditions and requirements incorporated
- herein, the Commission hereby licensgp -the Niagara Mohawk Power Corporation:
Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess,
- use, and operate the facility at-the designated location in Oswego County, New York, in accordance with the procedures and limitations set forth in this license; (2)
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 as of February 4, 1976; (3) 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 s'ources for reactor instru-mentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; P cl/
)q y-/0 g ~ i avJgg ~ g VCp pl" ~ ' v ~ ~ ~ ~ 0 'Ip (4) Pursuant to the Act and 10 C}'R Parts 30, 40 nnd 70, to ~ receive, pos css and>>sc in amounts as required any byproduct, ourcc or special nuclear material Mithout ,restriction to chemical or physical form, for sample 'naly is or ~instrument and equipment calibration or associated vith radioactive apparatus or components. ~ ~ (5) Pursuant to the Act and 10 CFR Parts 30-and 70, to possess but not separate, such byproduct and special nuclear raterials as may be produced by the operation of the Jacility." ~ ~r % ~ I ~ Tlds license shall be, deemed to contain and is subject to tie conditioiis "pecified in the follo~<ng Co~ssion reoulations $a 10 CPR Chaoter I: Part 20, Section 30.34 of Part 30; Section 40.41 of Part 40; Sect'ion'50.54 aid 50.59 of Part 50; and Section 70.32-of P rt 70. The 'license is subject to all a licable provisions. o= th Act and to the rules, regulatiors, and orders of the Co~~ssion nor or hereafter in effect and is also cubject to the additional conditions specified or incorporated belov>> ~ W ~ ~ '() ~ j ~et ~ - 5.'he licensee is authori"ed to operate the facility at steady state reactor core pover levels not in excess of 1850 mega~at ts (thecal). ~ (2) Technical S ecifications The Technical Specifications contained iq A indices A and B, as revised through Amendment No. 54'are hereby incorporated in the license. The hc see shall operate the facility in accor'dance with the Technical Specifications. 0 ~ ther -of-c the e power s lim> e cl e 0 re o co i ) In ea o ceo ation 1n i core p er 1 el the coastd redu d f n mode has b edwa r e egun, is no I a' e.i, lf Pg'~S I 'ff )~ >!'-:.'< i j5al'.gg ,8Ãf "f9QQB;> f&P~9i3<';<< ~ q~Q "s yCg 3i (f,"L J'.s"l" flh'"~ >0 .",~ UP~'c. "rV, ~33 ]k;- ,R ", tl'g > ~ i ld(>ik, H (3) Beyond the point in the Cycle 6 fuel cycle at which the reactivity reduction rate during a scram $ s less than that of the curve marked EOC 6 minus 1500 Nwd/T ln Figure 2C of "Supplemental Reload L1censlng Submittal f'or N.lne Nile point flfN Nuclear power Station Unit 1 Reload No. 1 ~ Ring Reanalysfs Supplement." NEDO 24155-1.Supplement 1 dated December 1978. operation of the reactor shall not exceed a core thermal power of 1813 megawatts (98K of rated) at rated flow con-ditions. Beyond the point in the Cycle 6 fuel cycle at which the reactivity reduction rate during a scram is less than that of the curve marked EOC 6 minus 1000 Mwd/T in Figure 2B of "Supplemental Reload Licensing Submittal for Nine Mile Point Nuclear Power Station (Unit 1) Reload No. 7," NEDO : 24155, 78NE0291, dated November 1978, operation of the reactor shall'ot exceed a core therma1 power of 1757 megawatts (955 of rated) at rated flow conditions. Operation beyond the end-of-cycle (all rods out condition) thermal power is limited to seventy (70) percent minimum'. Increasing core power level via reduced feedwater heating, once operation in the coastdown mode has begun, is not allowed. h ~ J c'~""0 f'b 'kgb" 7 , <'qll ~ f f ~ ff IP "d l>>'" <ff) P"', f f'. f ~f ~ ~ '7 'Xhis )fc<<nsc is subject go the folio>:io~ additicoal. conditions fo" the protection of the covi~~t: '(1) The )iccnscd ~ill co=plcte construction of' ncv raduaste facility in conformance Mith the design def iocd and cva)uated ~ 5a the FES, to be operational no later than June )976. Pursuant to Section 401(d) of the Federa) Mater Pollution Control Act P en'd=ents of l972; this permit is subject to the require-ents set forth in a certification dated April 9, 1974, issued to thc lice'nsce by the"State of New York. 'nclusion of the State requirements herein shall not relieve licensee of its obligation to obtain Co~ission approval, pursuant to the Ac't and regulations promulgated pursuant thereto, of any intake or discharge design which may ultimately be required by the State of ~- Nev York. (3) Pursuant to Section 402 of the Federal.'~~ater Pollution Control Act Amendnents of 1972, this perait is subject to the requ'ircments that mill be sat forth in a certification to"be issued to the licensee by thc Znvizonaeotal Protection Agency (EPA). Tnclusion of the EPA requirements herein shall not relieve licensee of its obligation to obtain 'Co~aissian approval, pursuant to the Act and regulations promulgated, pursuant thereto, of any intake or discnarge design or alternate heat dissipation system vhich may ultiiiately - 'e required by the. Environ~er~tal Protection Agency. (4) Securit Plan Guard Trainin and Safe uards Contin encv Plans The licensee shall implement and maintain in effect all provisions of the Comnission-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 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Nine M'.le Point Nuclear Station Physical Security Plan," with revisions submitted through December 29, 1987; "Nine Mile Point Nuclear Station Guard Training and Qualification Plan," with revisions submitted through June 27, 1985; and "Nine Mile Point Nuclear Station Safeguards Contingency Plan," (Chapter 8 of the Physical Security Plan) with revisions submitted through July 30, 1987. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. Paragraph 2.0(5) of the license has been combined with paragraph 2.D(4) as amended above into a single paragraph. h y 1 4 ~ ' A ,'r ~,, r IT I licensee shall fully implement and maintain $ n effect. prov ons of the Cormnission-approved Guard Training gualific n Plan, including amendments and chan made pursuant to the author'f 10 CFR 50.54(p). The app ed plan consists of documents wit d from public disclos pursuant to 10 CFR 73.2l identified as e Nile Point ear Station Security Training and gualification an" d d August 17, 1979 as revi ed June 26 and Decemb . 1981. This plan shall be implemented, in a rdance th 10 CFR 73.55(b)(4), within 60 days after a oval by the C 'ssion. The licensee may make changes t is plan without prior; ission approval if th anges do not decrease the safe 'rds effectiven of the plan. The licensee shall-main records of and it reports concerning such changes in the sam man as required for, changes made to the Safeguards Conting an pursuant to 10 CFR 50.54(p). 2.D{6) Recirculation S stem Safe-end Re lacement The recirculation system and safe-end replacement program including the cutting and welding of the replacement components and the dose mitigation program (ALARA) is approved, subject to the following conditions: a. 'The licensee shall complete the recirculation piping stress reanalysis prior to restart of Nine Mile point Nuclear Power Station, Unit'o. l. The results of this analysis for selected representative portions of the recirculation system shall be submitted to the NRC prior to restart of the facility. C b. All fuel and control rods shall be removed from the reactor pressure vessel and stored in the spent fuel pool during the period that work on the safe-end and recirculation system replacement program is in progress. c. The licensee shall update the collective occupational dose estimate weekly. If the updated estimate exceeds the 1908 person-rem estimate by more than 10%, the licensee shall provide a revised
- estimate, including the reasons for such changes, to the NRC within 15 days of determination.
d. Progress reports shall be provided at 90-day intervals from June '30, 1982 and due 30 days after close of the interval, with a final report within 60 days after completion of the r epair. These reports will conclude: (1) a sutomary of the occupational dose received to date by major task, and (2) a comparison of estimated doses with the doses actually received. 1 II I, 1 p 1 lt 't~, ~~. Fire Protection g 0'"1. The licensee may proceed with and is required to complete the mod-e aCE, ifications identified in Table 3.1 of the NRC's Nine Nile Point " " ~pip L>> Unit 1 Safety Evaluation Report (SER), Fire Protection
- Review, gsc
~8 pP dated Jul>> 26, 1979. These modifications shall be completed cy in accordance with the schedule in Table 3.1 of the SER or supple-ge'< '1U @ ments thereto. I if+
- Further, Niagara Mohawk Power Corporation shall, prior to implementation, provide for Commission review and obtain Commission approval of the final design of modifications as indicated in section 3.1 of the Safety Evalyation Report.
Except for the modifications described in the approved fire protection plan and approved as a result of Commission review of the Nine Mile Point Unit 1 Nuclear Plant Fire Protection
- Program, Niaoara Mohawk Power Corporation is authorized to make changes to the Program without prior Commission approval provided that such changes do not result'in a decrease in C
t e Pro ram. ihe ef i ects veness of h g The licensee is required to implement the administrative controls identified in Section 6 of the SE. The administrative controls shall be in effect by September 1, 1979. 2.D.(8) Hot Process Pi e Penetrations (a) An unide'ntified leakage limit of a change of 1 gallon per minute in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit operation will be imposed by 'dministrative control.(Standing Order) at the facility for the interim period. (b) Th'e licensee shall restore the facility to a condition consistent with.the FSAR or provide a change to the FSAR criteria for staff review and approval prior to re'start from the forthcoming Cycle 8'.outage. Not Process Pipe Penetrations in the Emergency Condenser Steam Supply (2 each), Main Steam (2 each), Feedwater (2 each), Cleanup Suction ( 1 each), and Cleanup Return (1 each) piping systems have 'een identified as not fully in conformance with FSAR design criteria.. This anomaly in. design condition from the original design is approved for the duration of Cycle '8 or until March 31, 1986,. whichever-occurs first, subject to the following conditions: ~ ~ s Addcd. t 6l And/, ub'~g I-Pg4 This 1icense is effective as on April 11., 2005. pA fo ~
Attachment:
Appendices A & B-Dire
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.. T'echnical Specif ications
. 'ate M'ssuance:
'December 26< 19l4
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of the.'date. of is vance and shyll e>:pire FOR.'ZEE ATONIC ZH"..GY.COWfXSSXON
- iambusso, Deputy Director r Reactor projects ctorate of X.icensing
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