ML17056C054
| ML17056C054 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/02/1992 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056C055 | List: |
| References | |
| NUDOCS 9210130097 | |
| Download: ML17056C054 (24) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATIO DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
132 License No.
DPR-63 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by. Niagara Mohawk Power Corporation (the licensee) dated January 7,
- 1992, complies with the standards 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; 2.
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 Commission's regulations and all applicable requirements have been satisfied.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-63 is hereby amended to read as follows:
r 9210130097 921002 PDR ADOCK 05000220 P
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 132, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
Accordingly, page 5 of Facility Operating License No.
DPR-63 is hereby amended to read as follows:*
2.D.(7)
Fire Protection 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 (Updated) for the facility and as approved in the Fire Protection Safety Evaluation Report dated July 26,
- 1979, and in the fire protection Exemption issued March 21, 1983, 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.
- 4. This license amendment is effective as'f the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Attachments:
1.
Page 5 of license 2.
Changes to the Technical Specifications Date of Issuance:
Robert A. Capra, Director Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
~g<<hg,f l,f hp 1
11 fl this change.
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2.D.(7)
Fi Pr i
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 (Updated) for the facility and as approved in the Fire Protection Safety Evaluation Report dated July 26,
- 1979, and in the fire protection Exemption issued March 21,
- 1983, subject to the following provision:
Niagara Mohavk Pover Corporation may make changes to the approved Fire Protection Program vithout prior approval of the Commission only if those changes vould not adversely affect the ability to achieve and maintain safe shutdovn in the event of a fire.
2.D.(8)
Ho Pr Pi P n ra i n Hot Process Pipe Penetrations in the Emergency Condenser Steam Supply (2 each),
Main Steam (2 each),
Feedvater (2 each),
Cleanup Suction (1 each),
and Cleanup Return (1 each) piping systems have been identified as not fully in conformance vith 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, vhichever occurs first, subject to the folloving conditions:
(a)
An unidentified 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 vill be imposed by administrative control (Standing Order) at the facility for the interim period.
(b)
The licensee shall restore the facility to a condition consistent vith the FSAR or provide a change to the FSAR criteria for staff reviev and approval prior to restart from the forthcoming Cycle 8 outage.
E.
This license is effective as of the date of issuance and shall expire on August 22, 2009.
FOR THE ATOMIC ENERGY COMMISSION Original Signed by Attachments Appendices A & B-Technical Specifications Date of Issuancei December 26, 1974 A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Amendments PS,
$$, ~132
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
132 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es Insert Pa es iiia 4a 241m 241n 241o 241ol 24lo2 24lo3 24lo4 24lo5 241o6 241p 24lq 241ql 241r 241s 24lsl 24lt 24ltl 24lu 241v 241w 24lx 24ly 241yl 24lz 24laa 241bb 24lcc 24ldd 241dd1 24ldd2 24ldd3 24ldd4 245a 246 255 260 265a iii a 4a 241m Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted Page deleted 245a 246 255 260 265a
SECTION 3.6.5 Radioactive Material Sources 3.6.6 (Deleted) 3.6.7 (Deleted) 3.6.8 (Deleted) 3.6.9 (Deleted) 3.6.10 (Deleted) 3.6. 12 Reactor Protection System Motor Generator Set Honitoring 3.6.11 Accident Monitoring Instrumentation DESCRIPTION 4.6.5 4.6.6 4.6.7 4.6.8 4.6.9 4.6.10 4.6.11 4.6.12 Radioactive Material Sources (Deleted)
(Deleted)
(Deleted)
(Deleted)
(Deleted)
Accident Honitoring Instrumentation Reactor Protection System Hotor Generator Set Monitoring PAGE 241k 241ee 241iil 3.6.13 Remote Shutdown Panels 4.6.13 Remote Shutdovn Panels 241ii4 3.6.15 Radioactive Effluents 3.6.16 3.6.17 Radioactive Effluent Treatment Systems Explosive Gas Hixture 3.6.18 Hark I Containment 3.6.19 Liquid Vaste Holdup Tanks 3.6.20 Radiological Environmental Honitoring Program 4.6.15 4.6.16 4.6.17 4.6.18 4.6.19 4.6.20 3.6.14 Radioactive Effluent Instrumentation 4.6.14 Radioactive Effluent Instrumentation Radioactive Effluents Radioactive Effluent Treatment Systems Explosive Gas Hixture Hark I Containment Liquid Vaste Holdup Tanks Radiological Environmental Honitoring Program 24ljj 24lvv 241qqq 241ttt 241vvv 241xxx 24lzzz 3.6.21 Interlaboratory Comparison Program 3.6.22 Land Use Census 4.6.21 4.6.22 Interlaboratory Comparison Program Land Use Census 241111 241nnnn Amendment ttn. ~~PZ,3tdP1 132 iiia
1.16 (Deleted) 1.17 (Deleted) 1.18 Gaseous Radwaste Treatment S stem A gaseous radwaste treatment system is any system designed and installed to reduce radioactive gaseous effluents by collecting main condenser offgas and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
1.19 Member s of the Public Member(s) of the public shall include persons uho are not occupationally associated uith the Nine Nil+
Point Nuclear Station.
This category does not include employees of Niagara Hohawk Power Corporation, the New York State Power Authority, its contractors or vendors who are occupationally associated with Nine Hile Point Unit 1.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with Nine Mile Point Unit l.
1.20 Hilk Sam lin Location A milk sampling location is that location where 10 or more head of milk animals are available for the collection of milk samples.
1.21 Offsite Dose Calculation Hanual ODCH The Offsite Dose Calculational Manual shall contain the current methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the environmental radiological monitoring program.
Amendment No.+ ~, P6 132 4a
Pages 241m through 241dd4 deleted.
Amendment No.+PS 132 241m
Onsite and Offsite Or anization (Cont'd).
d.
The persons responsible for the training, health physics and quality assurance functions may report to an appropriate manager onsite, but shall have direct access to responsible corporate management at a level where action appropriate to the mitigation-of training, health physics and quality assurance concerns can be accomplished.
Facilit Staff 6.2.2 The unit organization shall be subject to the following:
a ~
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
During reactor operation, this licensed operator shall be present at the controls of the facility.
C ~
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.
d.
An individual qualified in radiation protection* procedures shall be on site when fuel is in the reactor.
The requirement for a Radiation Protection qualified individual may be less than the minimum requirement for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected
- absence, provided immediate action is taken to fillthe required position.
Amendment Nn. +$8',38lf 132 2'45a
Facilit Staff (Cont'd) e.
A licensed Senior Reactor Operator shall be required in the Control Room during power operations, hot shutdown, and when the emergency plan is activated.
This may be the Station Shift Supervisor-Nuclear or the Assistant Station Shift Supervisor-Nuclear or another Senior.
Reactor Operator during power operations or hot shutdown.
Mhen the emergency plan is activated during normal operations or hot shutdown, the Assistant Station Shift Supervisor-Nuclear becomes the Shift Technical Advisor and the Station Shift Supervisor-Nuclear is restricted to the control room until an additional licensed Senior Reactor Operator arrives.
f.
A licensed Senior Reactor Operator shall be responsible for all movement of new and irradiated fuel within the site boundary.
All core alterations shall be directly supervised by a licensed senior reactor operator who has no other concurrent responsibilities during this operation.
A Licensed Operator will be required to manipulate the controls of all fue handling equipment except movement of new fuel from receipt through dry storage.
All fuel moves within the core shall be directly monitored by a member of the reactor analyst group.
g.
DELETED h.
Administrative procedures shall be developed and implemented to limit the working hours of facility staff who perform safety-related functions; e.g.,
licensed Senior Operators, licensed Operators, health physicists, auxiliary operators and key maintenance personnel.
Adequate shift coverage shall be maintained without routine heavy use of overtime.
The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the facility is operating.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for.
refueling, major maintenance or major plant modifications on a temporary basis, the following guidelines shall be followed:
Amendment No. ~P6,gCJld,~
132 246
Activities (Cont'd) 6.5.2.9 The Plant Hanager shall-assure the performance of a reviev by a qualified individual/organization of changes to the Radiological Vaste Treatment systems.
6.5.2.10 Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forvarding of these reports to the Vice President Nuclear Generation and to the Safety Reviev and Audit Board.
6.5.2.11 Reviev of changes to the Process Control Program and the Offsite Dose Calculation Hanual.
Approval of any changes shall be made by the Plant Hanager or his designee before implementation of such changes.
6.5.2.12 Reports documenting each of the activities performed under Specifications 6.5.2.1 through 6.5.2.9 shall be maintained.
Copies shall be provided to the Vice President-Nuclear Generation and the Safety Reviev and Audit Board.
6.5.2.13 The Plant Hanager shall assure the performance of a review by a qualified individual/organization of the Fire Protection Program and implementing procedures at least every 12 months and submittal of recommended changes to the Safety Reviev and Audit Board.
6.5.3 Safet Reviev and Audit Board SRAB Function 6.5.3.1 The Safety Reviev and Audit Board shall function to provide independent reviev and, audit of designated activities in the areas of:
a.
nuclear pover plant operations b.
nuclear engineering c.
chemistry and radiochemistry d.
metallurgy e.
instrumentation and control f.
radiological safety g.
mechanical and electrical engineering h.
quality assurance practices i.
(other appropriate fields associated vith the unique characteristics of the nuclear power plant)
Amendment ttn. ~$6/5,old,Pllf,3211 132 255
6.6 Re ortable Occurrence Action 6.6.1 The folloving actions shall be taken for REPORTABLE EVENTS:
a ~
The Commission shall be notified and a report submitted pursuant to the requirements of Sections 50.72 and 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be revieved by the SORC and the results of this reviev submitted to the SRAB and the Vice President Nuclear Generation.
6.7 Safet Limit Violation 6.7.1 The folloving actions shall be taken in the event a Safety Limit is violated:
aO The provisions of 10 CFR 50.36(c)(l)(i) shall be complied vith immediately.
b.
The NRC Operations Center shall be notified by telephone as soon as possible and in a cases vithin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President Nuclear Generation and the SRAB shall be notified vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C ~
A Safety Limit Violation Report shall be prepared.
The report shall be revieved by the SORC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, vithin 30 days of the violation, and to the SRAB, and the Vice President Nuclear Generation vithin 14 days.
6.8 Procedures 6.8.1 Mritten procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix "A" of USAEC Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 belov.
a.
Vritten procedures shall be established, implemented, and maintained for activities involving the Fire Protection Program implementation.
6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be revieved and approved by the Plant Manager or designee prior to implementation and periodically as set forth in administrative procedures.
Amendment No. Q,g,+PI,+1 132 260
3)
NEDO-20556-P-A "GENERAL ELECTRIC COMPANY ANALYTICALMODEL FOR LOSS-OF-COOLANT ACCIDENT ANALYSIS IN ACCORDANCE MITH 10CFR50 APPENDIX K".
(Latest approved revision)
.3 The core operating limits shall be determined such that all applicable limits (e.g., fuel therma1-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.
.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements shall be
- provided, upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
6.9.2 Fire Protection Pro ram Re orts Noncompliances with the Fire Protection Program (as described in the Final Safety Analysis Report) that adversely affect the ability to achieve and maintain safe shutdown in the event of a fire shall be reported in accordance with the requirements of 10CFR50.72 and 10CFR50.73.
Amendment Nn. ~132 265a