ML17056A112
| ML17056A112 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/10/1989 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056A113 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 8907180453 | |
| Download: ML17056A112 (38) | |
Text
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0 UNITE0 STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 108 License No. DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated June 3, 1988, as amended September 28 and November 15, 1988, 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; B.
C.
The facility will the provisions of the Commission; There is reasonabl by this amendment and safety of the conducted in compl operate in conformity with the application, the Act, and the rules and regulations of e assurance (i) that the activities authorized can be conducted without endangering the health public, and (ii) that such activities will be iance 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 a'll applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated i'n 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:
85'07180453 89'07 f0 PDR ADOCK 05000220 P
(2)
Technical S ecifications The Techni ca 1 Speci fications conta ined in Appendices A and B, as revised through Amendment No. 108, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 10.
1989 Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects, I/II
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
108 TO FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET N0.=50-220 Revise Appendix A as fo11ows:
Remove-Pa es 245 247 248 249 252 253 254 255 258 259 260 261 26la 265 266 Insert Pa es 245 245a 247 248 249 252 253 254 255 258 259 260 261 26la 265 266
- 6. 0 ADNINISTRATIVE CONTROLS 6.
6.1.1 The General Superintendent
- Nuclear Generation shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 6.1.2 The Station Shift Supervisor - Nuclear (or during his absence from the control
- room, a designa'ted individual) shall be responsible for the control room command function.
A management directive to this effect, signed by the Executive Vice President - Nuclear Operations shall be re-issued to station personnel on an annual basis.
Onsite and Offsite Or anization 6.2.1 An onsite and an offsite organization shall be established for unit operation and corporate management.
The onsi te and offsi te organization shall include the positions for activities affecting the safety of the nuclear power plant.
Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intdrmediate levels to and including all operating organization positions.
Those relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions or in equivalent forms of documentation.
The organization charts shall be documented in the Final Safety Analysis Report, and the functional descriptions of departmental responsibilities and relationships and job descriptions for key personnel positions are documented in procedures.
b.
The Executive Vice President Nuclear Operations shall have corporate responsibility for overall plant nuclear safety.
The Executive Vice President Nuclear Operations shall take any measures needed to assure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.
c.
The General Superintendent
- NuclearGeneration shall have responsibility for overall unit operation and shall have control over those resources necessary for safe operation and maintenance of the plant.
Amendment No.
245
7
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.
Faci 1 it 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.
d.
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.
An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
The Radiation Protection qualified individual and Fire Brigade composition may be less than the minimum requirements 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 fill the required positions.
Amendment No.
108 245a
)
ff (C
'd) 1)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight (excluding shift turnover time).
2)
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period (all excluding shift turnover time).
3)
A break of at least 8-hours should be allowed between work periods (including shift turnover time).
4)
Except during extended shutdown periods,- the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above-guidelines shall be authorized by the Plant Superintendent, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the General Superintendent Noclear Generation or designee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
The Superintendent Operations Nuclear, Assistant Superintendent Operations Nuclear, Station Shift Supervisor Nuclear and Assistant Station Shift Supervisor Nuclear shall hold senior reactor operator l.icenses.
Amendment No.~,
108 247
FIGURE OELETEO Amendment Nos. jhow, /, @,
108 248
FIGURE DELETED Amendment No. $5',
108 249
Alternates 6.5.1.3 Heetin Fre uenc Alternate members shall be appointed in writing by the SORC Chairman to serve on a temporary basis;
- however, no more than two alternates shall participate in SORC activities at any one time.'.5.1e4 The SORC shall meet at least once per calendar month and as convened by the SORC Chairman.
uorum 6.5.1.5 A quorum of the SORC shall consist=of the Chairman and four members including alternates.
Res onsibilities 6.5.1.6 The Site Operations Review Committee shall be responsible for:
a.
Review of all REPORTABLE EVENTS.
b.
Review of unit operations to detect potential safety hazards.
C.
d.
Performance of special reviews investigations or analyses and reports thereon as requested by the Chairman of the Safety Review and Audit Board.
Investigation of violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Executive Vice President Nuclear Operations and to the Safety Review and Audit Board.
Amendment No. ~,
tne 252
A~nthori t 6.5.1.7 The Site Operations Review Committee shall:
a.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6 (a) through (d) above constitutes an unreviewed safety question.-
Records b.
Provide immediate written notification to the Executive Vice President Nuclear Operations and the Safety Review and Audit Board of disagreement between the SORC and the General Superintendent Nuclear Generation;
- however, the General Superintendent Nuclear Generation shall have the responsibility for resolution of such disagreements pursuant to 6.1.1 above.
6.5.1. B The Site Operations Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Executive Vice President Nuclear Operations and the Safety Review and Audit Board.
6.5.2 Technical Review and Control Activities 6.5.2.1 6.5.2.2 Each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes
- thereto, shall be prepared by a qualified individual/organization.
Each such procedure, and changes
- thereto, shall be reviewed by an individual/group other than the individual/group which prepared the procedure, or changes
- thereto, but who may be from the same organization as the individual/group which prepared the procedure, or changes thereto.
Approval of procedures and programs and changes thereto and their safety evaluations, shall be controlled by administrative procedures.
Proposed changes to the Technical Specifications shall be prepared by a qualified individual/organization.
The preparation of each proposed Technical Specifications change shall be reviewed by an individual/group other than the individual/group which prepared the proposed
- change, but who may be from the same organization as the individual/group which prepared the proposed change.
Proposed changes to the Technical Specifications shall be approved by the General Superintendent-Nuclear Generation.
Amendment No.
P5 108 253
I
Activities (Cont'd) 6.5.2.3 6.5.2.4 6.5.2.5 6.5.2.6 6.5.2.7 6.5.2.8 Proposed modifications to unit structures, systems and components that affect nuclear safety shall be designed by a qualified individual/organization.
Each such modification shall be reviewed by an individual/group other than the individual/group which designed the modification, but who may be from the same organization as the individual/group-which designed the modification.
Proposed modifications to structures, systems and components and the safety evaluations shall be approved prior to implementation by the General Superintendent-Nuclear Generation; or the Station Superintendent-Nuclear Generation; or the Technical Superintendent-Nuclear Generation as previously designated by the General Superintendent-Nuclear Generation.
Individuals responsible for reviews performed in accordance with Specifications 6.5.2.1, 6.5.2.2 and 6.5.2.3 shall be members of the station supervisory staff, previously designated by the General Superintendent-Nuclear Generation to perform such reviews.
Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.
If deemed necessary such review shall be performed by the appropriate designated station review personnel.
Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications and their safety evaluations shall be reviewed by the General Superintendent-Nuclear Generation; or by the Station Superintendent-Nuclear Generation, or the Technical Superintendent-Nuclear Generation as previously designated by the General Superintendent-Nuclear Generation.
The General Superintendent-Nuclear Generation shall assure the performance of special reviews and investigations, and the preparation and submittal of reports
- thereon, as requested by the Executive Vice President Nuclear Operations.
r The facility securi ty program, and implementing procedures, shal 1
be reviewed at least every 12 months.
Recommended changes shall be approved by the General Superintendent-Nuclear Generation and transmitted to the Executive Vice President Nuclear Operations, and to the Chairman of the Safety Review and Audit Board.
The facility emergency
- plan, and implementing procedures shall be reviewed at least every 12 months.
Recommended changes shall be approved by the General Superintendent-Nuclear Generation and transmitted to the Executive Vice President Nuclear Operations and to the Chairman of the Safety Review and Audit Board.
Amendment No.~,
tpp 254
r h
I
Activities (Cont'd) 6 ~ 5.2.9 The General Superintendent-Nuclear Generation shall assure the performance of a review by a qualified individual/organization of changes to the Radiological Haste 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 forwarding of these reports to the Executive-Vice President Nuclear Operations and to the Safety Review and Audit Board.
6.5.3 Function
. 6.5.2. 11 Review of changes to the Process Control Program and the Offsi te Dose Calculation Manual.
Approval of any changes shall be made by the General Superintendent Nuclear Generatio'n 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 Executive Vice President Nuclear Operations and the Safety Review and Audit Board.
Safet Review and Audit Board (SRAB) 6.5.3.1 The Safety Review and Audit Board shall function to provide independent review and audit of designated activities in the areas of:
a.
b.
C.
d.
e.f.
g.
h.
1.
nuclear power plant operations nuclear engineering chemistry and radiochemistry metallurgy instrumentation and control radiological safety mechanical and electrical engineering quality assurance practices (other appropriate fields associated with the unique characteristics of the nuclear power plant)
Amendment Nos. P5, P6 108 255
Audi ts 6.5.3.8 Audits of facility activities shall be performed under the cognizance of the SRAB.
These audits shall encompass:
a.
The conformance of facility operation to all provisions contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The performance, training and qualifications of the entire facility staff at least once per year.
C.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
d.
The performance of all activities required by the guality Assurance Program to meet the criteria of Appendix "B", 10CFR50, at least once per two years.
e.
The Facility Emergency Plan and implementing procedures at least once every 12 months.
f.
The Facility Security Plan and implementing procedures at least once every 12 months.
g.
The Facility Fire Protection Program and implementing procedures at least once per two years.
- h. 'ny other area of facility operation considered appropriate by the SRAB or the Executive Vice President Nuclear Operations.
i.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
j.
The Offsite Dose Calculation Manual and implementing procedures at least once per 24 months.
k.
The Process Control Program and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.
Amendment Nos. P5 P6,Pf,j3d, 108 258
A~othorit 6.5.3.9 Records The SRAB shall report to and advise the Executive Vice President Nuclear Operations on those areas of responsibility specified in Section 6.5.3.7 and 6.5.3.8.
6.5.3.10 Records of SRAB activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each SRAB meeting shall be prepared, approved and forwarded to the Executive Vice President Nuclear Operations within 30 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.3.7 e,f,g and h above, shall be prepared, approved and forwarded to the Executive Vice President Nuclear Operations within 14 days following completion of the review.
c.
Audit reports encompassed by Section 6.5.3.8
- above, shall be forwarded to the Executive Vice President Nuclear Operations within 90 days following completion of the review.
Amendment Nos.
259
6.6 Re ortable Occurrence Action The following 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 10CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the SORC and the results of this review submitted to the SRAB and the Executive Vice President Nuclear Operations.
6.7 Safet Limit Violation The following actions shall be taken in the event a Safety Limit is violated:
a.
The provisions of 10 CFR 50.36(c)(1)(i) shall be complied with immediately.
b.
The Safety Limit violation shall be reported to the Commission, the Executive Vice President-Nuclear Operations and to the SRAB immediately.
C.
d.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed 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.
The Safety Limit Violation Report shall be submitted to the Commission, within 30 days of the violation, and to the SRAB, and the Executive Vice President Nuclear Operations within 14 days.
6.8 Procedures 6.8.1 Hritten 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 below.
6.8.2 Each procedure and administrative policy of 6.8.1
- above, and changes
- thereto, shall be reviewed and approved by the General Superintendent-Nuclear Generation or designee prior to implementation and periodically as set forth in each document.
Amendment No. p6
~ Md 260
6.8 Procedures (Continued) 6.8.3 Temporary changes to procedures of 6.F 1 above may be made provided:
a.
The intent of the original procedure is not altered.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed and approved by the General Superintendent-Nuclear Generation or designee within 14 days of implementation.
6.9 Re ortin Re uirements In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted in accordance with 10 CFR 50.4.
P.P.
~tl I
t'tt t,
A I
p pl t
Ip I
I I
>>I submitted following (1) receipt of an operating
- license, (2) amendment to the license involving a planned increase power level, '(3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have
'ignificantly altered the nuclear, thermal, or hydraulic performance of the plant.
The report shall address each of the tests identified in the FSAR and shall in general include a
description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
Amendment No.~,
108 261
t
~
l
= 6.9.1 Startup reports shall be submitted within (1) 90 days following completion of the startup test
- program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operatii n), supplementary reports shall be submitted at least every three months until all three
--vents have been completed.
b.
Annual Occu ational Ex osure Re ort.
A tabulation shall be submitted on an annual basis which includes the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work.and job functions, 1/ e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totaling less than 20K of the individual total. dose need not be accounted for.
In the aggregate, at least 80'X of the total whole body dose received from external sources shall be assigned to specific major work functions.
c.
Honthl 0 eratin Re ort.
Routine reports of operating statistics and shutdown experience including documentation of challenges to the safety relief valves or safety valves, shall be submitted on a monthly basis, which will include a narrative of operating experience, in accordance with 10 CFR 50.4, no later than the 15th of each month following the calendar month covered by the report.
1/
This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
Amendment No. P5, ~,
108 261a
~
~
I
6.9.1 Changes to the Offsite Dose Calculation Hanual (ODCH):
Shall be reported to the Commission in the.
Semiannual Radioactive Effluent Release Report. for the period in which the change(s) was made effective.
This submittal shall contain:
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information submitted should consist of a package of those pages of the Offsite Dose Calculation Hanual to be changed, together with appropriate analyses or evaluations justifying the change(s);
b.
C.
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and Documentation of the fact that the change has been reviewed and found acceptable.
6.9.2 Fire Protection Program Reports a.
Submit a special report in accordance with 10 CFR 50.4 as follows:
Notify the Regional Administrator of the appropriate Regional. Office by teleph'one within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Confirm by telegraph, mai lgram or fascimile transmission no later than the first working day following the event, and Follow-up in writing within 14 days after the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to an operable status.
b.
Submit a special report in accordance with 10 CFR 50.4 within 30 days following the event outlining the plans and procedures to be used to restore the inoperable equipment to an operable status.
Amendment No. $5, 108 265
~.
s l
6.9.3 Special Reports Special reports shall be submitted in accordance with 10 CFR 50.4 Regional Office within the time period specified for each report.
These reports shall be submitted covering the activities.
identified below pursuant to the requirements of the applicable reference specification:
Reactor Vessel Material Surveillance Specimen Examination, Specification 4.2.2(b)
(12 months) b.
Safety Class 1 Inservice Inspection, Specification (See Table 4.2.6(a))
(Three months) c.
Safety Class 2 Inservice Inspections, Specification (See Table 4.2.6(b))
(Three months) d.
Safety Class 3 Inservice Inspections;- Specification (See Table 4.2.6(c))
(Three months) e.
Primary Containment Leakage Testing, Specification 3.3.3 (Three months) f.
Secondary Containment Leakage Testing, Specification 3.4.1 (Three months) g.
Sealed Source Leakage In Excess Of Limits, Specification 3.6.5.2 (Three months) h.
Calculate Dose from Liquid Effluent in Excess of Limits, Specification 3.6.15.a(2)(b)
(30 days from the end of the affected calendar quarter).
Calculate Air Dose from Noble Gases Effluent in Excess of Limits, Specification 3.6.15.b(2)(b)
(30 days from the end of the affected calendar quarter).
Calculate Dose from I-131, H-3 and Radioactive Particulates with half lives greater than eight days in Excess of Limits, Specification 3.6.15.b(3)(b)
(30 days from the end of the affected calendar quarter).
~
~
~
~
Calculated Doses from Uranium Fuel Cycle Source in Excess of Limits, Specification 3.6.15.d (30 days from the end of the affected calendar year).
Inoperable Gaseous Radwaste Treatment System, Specification 3.6.16.b (30 days from the event).
Environmental Radiolo ical Re orts.'ith the level of radioactivity (as the result of plant effluents) in an environmental sampling medium exceedi ng the reporting level of Table 6.9.3-1, when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within thirty (30) days from the end of the calendar quarter a special report identifying the cause(s) for exceeding the limits, and define the corrective action to be taken.
Amendment No.~ I08 266