ML20065D959
| ML20065D959 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/31/1994 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065D963 | List: |
| References | |
| NUDOCS 9404070298 | |
| Download: ML20065D959 (23) | |
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UNITED STATES 4
4 NUCLEAR REGULATORY COMMISSION k...
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. w Assincron. o.c. 2 css >-cooi TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENS[
Amendment No. 178 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 7,1993, 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.
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.
9404070298 940331 PDR ADOCK 05000327 P
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9:
- - 2.
Accordingly, the first paragraph of License Condition 2.C.(23)A. of Facility Operating License No. 77 is hereby amended to read as follows:
TVA shall continue to provide an on-shift technical advisor to the shift operations supervisor.
-3.
Also-the license is amended by changes to the Technical Specifications-as indicated in Attachment 2 to this license amendment and paragraph' 2.C.(2) of Facility Operating License No.'DPR-77 is hereby amended to read as follows:
~
(2) Technical Soecifications The Technical Specifications contained in Appendices.A and'B, as revised through Amendment No.173, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
4.
This license amendment is effective as of its date of issuance, to be implemented within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION r
Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
1.
Page 10 of License
- 2.
Changes to the lechnical Specifications Date of Issuance:
March 31, 1994 1
4 Page 10 is attached for convenience, for the composite license to reflect this change.
v
/
10 -
i (23) TMI Action Plan Dated Conditions Each of the following conditions shall be completed to the satisfaction of the NRC by the times indicated:
A.
Shift Technical Adv.isor (Section 22.3. I. A.1.1)
TVA shall continue to provide an on-shift' technical advisor to the shift operations supervisor.
[
All STAS shall be fully trained no later than by January 1, 1981.
STAS shall complete eight weeks of mathematics, physics, thermodynamics, fluid flow, heat transfer, instrumentation and control,. chemistry, materials and structural analysis.
Following this, STAS shall receive two weeks of design review and five weeks of systems dynamic behavior. including transient analysis and techniques for transient identification. The training program for engineers designated as STAS shall consist of three portions: academic training in thermodynamics, fluid flow, heat transfer and reactor theory; specific instruction in plant systems and Technical Specifications; and finally, simulator training.
The training shall be taught at the college level and be equivalent to about'60 semester hours.
1 Items for completion by January 1,1981:
B.
Plant Shieldina (Section 22.3. II.B.2)
TVA shall complete modification to assure adequate access to vital areas and protection of safety equipment following an accident resulting in a degraded core.
C.
Auxiliary Feedwater Initiation and Indication (Section 22.3.
II.E.1.2)
(a)
TVA shall upgrade, as necessary, automatic initiation of the auxiliary feedwater system to safety-grade quality.
T A shall upgrade, as necessary, the indication of V
(b) auxiliary feedwater flow to each steam generator to 1
safety grade quality.
l D.
Additional Accident Honitorina Instrumentation (Section 22.3.
i II.F.1)
(1)
TVA shall install interim noble gas monitors at the first outage of sufficient duration.
Amendment No.
10, 178
+
ATTACHMENT 2 TO LICENSE AMENDMENT NO.178 FACILITY OPERATINP, LICENSE NO. DPR-77 DOCKET NO. 50-327-Revise the Appendix A Technical Specificatiens by removing the pages identified below and. inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT Index page.XVIII Index page XVIII 1-4 1 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6-5 6-6 6-6 6-8 6-8 6-11 6-11 6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-16 6-16 6 '6-22 6-23 6-23 6-24 6-24 6-25 6-25 s
)
'h
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE~
Consultants..................................................
6-10 Meeting Frequency..............................................
6-10 Quorum....................
6-10 Review.........................................................
6-10 Audits.........................................................
6-11 Authority......................................................
6 Records.......................
6-12 6.5.3 DELETED 6.6 REPORTABLE EVENT ACTI0N...........................................
6-14 6.7 SAFETY LIMIT VIOLATION............................................
6-14 6.8 PROCEDURES AND PR0 GRAMS...........................................
6-14 6.9 REPORTING REOUIREMENTS 6.9.1 ROUTINE REP 0RTS.................................................
6-17 6.9.2 SPECIAL REP 0RTS.................................................
6-21
- SEQUOYAH - UNIT 1 XVIII Amendment No. 58, 74.178
b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDAR7 LEAXAGE, or c.
Reactor coolant system leakage through a steam generator to the secondary system.
MEMBER (S) 0F THE PUBLIC 1.17 MEMBER OF THE PUBLIC means an individual in a controlled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.
OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.18 The OFFSITE DOSE CALCULATION MANUAL (0DCH) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent ~ monitoring alarm / trip setpcints. and in the conduct of the Radiologi-cal Environmental Monitoring Prograr.1. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Pro-grams required by Section 6.8.4 and (2) descriptions of the information that l
should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.8.
OPERABLE - OPERABILITY 1.19 A system, subsystem, train,- or component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, a normal and an-emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, com-ponent or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL MODE - MODE 1.20 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
PHYSICS TESTS 1.21 PHYSICS TESTS shall b'e those tests performed to measure the fundamental-nuclear characteristics of the reactor core and 'related instrumentation and a
- 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 1
1 10 CFR 50.59, or 3) otherwise approved by the Commission.
1 SEQUOYAH - UNIT 1 1-4 Amendment No. 12, 71, 148, 155, 169, 174, 178
c.
b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE B0UNDARY LEAKAGE, or c.
Reactor coolant system leakage through a steam generator to the secondary system.
MEMBER (S) 0F THE PUBLIC 1.17 MEMBER OF THE PUBLIC means an individual in a controlled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.
OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.18 The 0FFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiologi-cal Environmental Monitoring Program. The 00CM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Pro-grams required by Section 6.8.4 and (2) descriptions of the information that l
should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.8.
OPERABLE - OPERABILITY 1.19 A system, subsystem, train, or component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, a normal and an emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that an required for the system, subsystem, train, com-ponent or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL MODE - MODE 1.20 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and
- 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.
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SEQUOYAH - UNIT 1 1-4 Amendment No. 12, 71, 148, 155, 169, 174, 178 i
6.0 ADMINISTRATIVE CONTROLS' 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in' writing the succession to this responsibility during his absence.
6.1.2 The Shift Operations' Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room com-mand function.
A management directive to this effect, signed by the Site Vice President, shall be reissued to all station personnel on an annual' basis.
6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS An onsite and an offsite organization shall be established for unit operation and corporate management.
The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be estab-lished and defined from the highest management levels through inter-mediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the FSAR and will be updated in accordance with 10 CFR 50.71(e).
b.
The Senior Vice President, Nuclear Power shall have corporate respon-l sibility for overall plant nuclear safety. This individual shall take any measures needed'to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured, c.
The Plant Manager shall be responsible for overall unit safe opera-tion and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 FACILITY STAFF a.
Each on-duty unit shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Reactor Operator shall be in the unit Control Room when fuel is in the reactor.
In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.
SEQUOYAH - UNIT 1 6-1 Amendment No. 32, 58, 74, 152, 178
ADMINISTRATIVE CONTROLS c.
A Radiological. control technician # shall be onsite'when fuel is in the
- reactor, d.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
e.
A Fire Brigade of at least 5 members shall-be maintained onsite at all times.# The Fire Brigade shall not include the Shift Operations Super-l-
visor and 2 other members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.
f.
The Operations Superintendent shall hold a. Senior Reactor Operator -
- license, g.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (i.e., senior reactor operators, reactor operators, assistant unit
~
operators, Radiological Control, 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 unit is operating.
- However, in the event that unforseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refuel -
ing, major maintanance, or major plant modification, on a temporary basis the following guidelines shall be followed:
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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 in. advance by the Plant Manager or his designee, in accordance with approved administrative.
procedures, or by 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 Plant Manager or his designee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
- The Radiological Control technician 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.
SEQUOYAH - UNIT 1 6-2 Amendment No. 32, 58, 74,152,.15f4 178
Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION WITH UNIT 2 IN MODE 5 OR 6 OR DE-FUELED Position Number of individuals required to fill position Modes 1, 2, 3, & 4 Modes 5 & 6 SOS l'
l' l
SRO 1
None R0 2
1 6
A0 2
2 STA 1
None WITH UNIT 2 IN' MODES 1, 2, 3, or 4 Postion Number of individuals required to fill position Modes 1, 2, 3, & 4 Modes 5 & 6 SOS l'
l' l
SR0 l'
None b
R0 2
1 6
A0 2
1 STA l'
None
' Individual may fill the same position on Unit 2.
60ne of the two required individuals may fill the same position on Unit 2.
l 1
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'SEQUOYAH - UNIT I 6-3 Amendment No. M, 58, 74,.178
TABLE 6.2-1 (Continued)
TABLE NOTATION j
SOS - Shift Operations Supervisor with a Senior Reactor Operators License on
'[
Unit 1 SR0 - Individual with a Senior Reactor Operators License on Unit 1 R0 - Individual with a Reactor Operators License on Unit 1 A0 - Auxiliary Operator STA - Shift Technical Advisor Except for the Shift Operations Supervisor, the Shift Crew Composition may be l
one less than the minimum requirements of Table 6.2-1 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 of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Com-position to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Operations. Supervisor from the Control Room
]
while the unit is in MODE 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room command function.
During any absence of the Shift Operations l
Supervisor from the Control Room while the Unit is in Mode 5 or 6, an indivi-dual with a valid SRO or R0 license (other than the Shift Technical Advisor) shall be designated to assume the Control Room command function.
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SEQUOYAH - UNIT 1 6-4 Amendment No. 58, 74,.178 1
1
ADMINISTRATIVE CONTROLS 6.2.3 INDEPEN0 TNT SAFETY ENGINEERING (ISE)
FUNCTION 6.2.3.1 The ISE shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISE shall be composed of at least 3 dedicated full-time engineers located onsite. These engineers will be supplemented as necessary by full-time engineers shared among all TVA nuclear sites to achieve an equivalent staffing of 5 full-time engineers performing the ISE functions applicable to Sequoyah.
RESPONSIBILITIES 6.2.3.3 The ISE shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 The ISE shall make detailed recommendations for revised procedures, equipment modifications, or other means of improving. plant safety to the Manager, Nuclear Experience Review / Independent Safety Engineering.
6.2.4 SHIFT TECHNICAL ADVISOR (STA) 6.2.4.1 The STA shall serve in an advisory capacity to the Shift Operations l
Supervisor on matters pertaining to the engineering aspects of assuring safe operation of the unit.
6.3 FACILITY STAFF OVALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions except for the. Site Radiological Control Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
l 1
- Not responsible for sign-off function.
SEQUOYAH - UNIT 1 6-5 Amendment No.- 12, 58, 74, 119, 152, 163, 178
ADMINISTRATIVE CONTROLS 6.4 TRAININGL 6.4.l~ A retraining and replacement training pr? gram for the facility staff shall be maintained under the direction of.the Plant Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55 and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.0 The Senior Vice President, Nuclear Power is responsible' for the safe operation of all TVA power plants.
6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 The PORC shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PORC shall be composed of the:
Chairman:
Plant Manager Member:
Operations Manager Member:
Radiological and Chemistry Manager l
Member:
Maintenance tianager Member:
Technical Support Manager Member:
Quality Audit and Assessment Manager Member:
Site Engineering Representative SEQUOYAH - UNIT-1 6-6 Amendment No. 58, 74, 152, 163, 178
4 ADMINISTRATIVE CONTROLS h.
Performance of special reviews, investigations or analyses and reports thereon.as requested by the Plant Manager or the Nuclear Safety Review Board.
i.
Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Site Vice. President and to the Nuclear Safety Review Board.
J.
Review of all proposed changes to the OFFSITE DOSE CALCULATION MANUAL.
l AUTHORITY 6.5.1.7 The PORC shall:
a.
Recommend in writing to the Plant Manager approval or disapproval of items considered under 6.5.1.6(a), (b) and (c) above.
b.
Require a determination in writing with regard to whether or not each item considered under 6.5.1.6(b), (c), and (e) above constitutes an unreviewed safety question.
c.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Site Vice Presi-dent and the Nuclear Safety Review Board of disagreement between'the PORC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the respon-sibility and authority provisions of these technical specifications.
Copies shall be provided to the Site Vice President and the Nuclear Safety Review Board.
6.5.lA TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.1A.I.
Activities which affect nuclear safety shall be conducted as follows:
a.
Procedures required by Specification 6.8.1 and other procedures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved.
Each such procedure or procedure change shall be reviewed by a qualified individual other than the. individual who prepared the procedure or procedure change, but who may be from the same organization as the individual who prepared the procedure or pro-cedure change.
Procedures shall be approved by.the appropriate responsible manager as designated in writing by the Plant Manager.
The Plant Manager, or Duty Plant Manager shall approve designated Administrative Procedures.
SEQUOYAH - UNIT 1 6-8 Amendment No. '58, 74,152,178
ADMINISTRATIVE CONTROLS f.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
g.
All REPORTABLE EVENTS.
h.
All recognized indications of an-unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety, i.
Reports and meetings minutes of the PORC.
l AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the NSRB. These audits shall encompass:
a.
The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire facility staff at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, d.
The performance of activities required by the Nuclear Quality
.[
Assurance Program to meet the criteria of Appendix "B",
10 CFR 50, at least once per 24 months.
e.
The Site Radiological Emergency Plan and implementing procedures at least once per 12 months.
f.
The Plant Physical Security Plan, the Safeguards Contingency Plan, and implementing procedures at least once per 12 months.
9 Any other area of unit operation considered appropriate by the NSRB-or the Senior Vice President, Nuclear Power.
h.
The Facility Fire Protection Program and implementing procedures at least once per 24 months.
i.
An independent fire protection and loss prevention program inspection and audit'shall be performed annually utilizing'either qualified offsite licensee personnel or an outside fire protection firm.
J.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
SEQUOYAH - UNIT 1 6-11 Amendment No. 68, 74, 178
t ADMINISTRATIVE CONTROLS k.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
1.
The OFFSITE DOSE CALCULATION MANUAL and implementing _ procedures at least once per 24 months.
t m.
The PROCESS CONTROL PROGRAM and implementing procedures for SOLIDIFICATION of radioactive wastes at least-once per 24 months.
n.
_The,oerformance of activities required by the Quality Assurance 1 Program to meet the criteria of Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev.1,1974 and Regulatory Guide 4.1, Rev. 1, 1975, at least once per 12 months.
AUTHORITY 6.5.2.9~ The NSRB shall report to and advise the Senior Vice' President,_ Nuclear Power those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NSRB meeting shall be prepared, approved and forwarded to the Senior Vice President, Nuclear Power within 14 days following each meeting.
b.
Reports of reviews encompassed by Section 6.S.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President, Nuclear Power within 14 days following" completion of the review.
c.
Audit reports encompassed by-Section 6.5.2.8 above, shall be for-4 warded-to.the Senior Vice President, Nuclear Power and to the manage-ment positions responsible for the areas audited within 30 days after completion of the audit.
6.5.3 THIS SPECIFICATION IS DELETED 1
l SEQUOYAH - UNIT 1 6-12 Amendment No. 42, 58, 74, 178 152.
- ;c-
' ADMINISTRATIVE CONTROLS' THIS PAGE IS BLANK
.l 1
SEQUOYAH - UNIT 1 6-13:
Amendment No. 58, 74 152, 178
ADMINISTRATIVE CONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the NSRB and the Site Vice President.
6.7 SAFETY LIMIT VIOLATION 6.7.1.The following actions shall be taken in the event a Safety Limit is violated:
a.
The unit shall be placed in at least HOT STANDBY within one hour.
b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Site Vice President and the NSRB shall be notified within 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 reviewed by the PORC.
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, the NSRB and the Site Vice President within.14 days of the violation.
6.8 PROCEDURES & PROGRAMS 6.8.1 Written procedures shall be established,. implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
SEQUOYAH - UNIT 1 6-14 Amendment'No. 36, 58, 74, 152, 178
ADMINISTRATIVE CONTROLS b.
Refueling operations.
c.
Surveillance and test activities of safety-related equipment.
d.
Plant Physical Security Plan implementation.
e.
Site Radiological Emergency Plan implementation.
f.
Fire Protection Program implementation.
9 PROCESS CONTROL PROGRAM implementation.
h.
Quality Assurance Program for effluent and environmental monitoring, l
using the guidance contained in Regulatory Guide 4.15, December 1977, or Regulatory Guide 1.21, Rev.1,1974 and Regulatory Guide 4.1, Rev. 1, 1975.
i.
OFFSITE DOSE CALCULATION MANUAL implementation.
l 6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as set forth in Specification 6.5.1A above.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
The intent of the original procedure is not altered.
a.
The change is approved by two members of the plant management staff, b.
at least one of whom holds a Senior Reactor Operator's License on the unit affected.
The change is approved in accordance with Specification 6.5.1A above c.
within 14 days of implementation.
6.8.4 The following programs shall be established, implemented, maintained, and changes thereto made in accordance with Section 6.5.1A:
Primary Coolant Sources Outside Containment a.
A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a The serious transient or accident to as low as practical levels.
6-15 Amendment No. 42, 58, 74, 148, 178 SEQUOYAH - UNIT 1
ADMINISTRATIVE CONTROLS systems include the safety injection system, residual heat removal system, chemical and volume control system, containment spray system, and RCS sampling system. The program shall include the following:
(i)
Preventive maintenance and periodic visual inspection requirements, and (ii)
Integrated leak test requirements for each system at refueling.
cycle intervals or less.
b.
In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine the airborne iodine concentrations in vital areas under accident ~
conditions. This program shall include the following:
(i) Training of personnel, (ii)
Procedures for monitoring, and (iii)
Provisions for maintenance of sampling and analysis equipment, c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:
(i)
Identification of a sampling schedule for the critical variables and control points for these variables, (ii)
Identification of the procedures used to measure the values of the critical variables, (iii)
Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps'for evidence of condenser in-leakage,-
(iv)
Procedures for the recording and management of data, (v)
Procedures defining corrective actions for off-control point -
chemistry conditions, (vi)
Procedures identifying (a). the authority responsible -for the -
interpretation of the data; and (b) the sequence and timing of administrative events required to initiate corrective action.
SEQUOYAH - UNIT 1 6-16 Amendment No. '58, 74,178'
ADMINISTRATIVE CONTROLS A supplemental report shall be prepared within 30 days after each subsequent failure during a valid demand for so long as the affected diesel generator unit continues to violate the criteria (3/20 or 6/100) for the reliability improve-ment program remedial action. The supplemental report.need only update the failure / demand history for the affected diesel generator unit since the last report for that diesel generator. The supplemental report shall also present an analysis of the failure (s) with a root cause determination, if possible, and shall delineate any further procedural, hardware or operational changes to be incorporated into the diesel generator improvement program and the schedule for implementation of those changes.
In addition to the above, submit a yearly data report on the diesel generator reliability.
6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.1 The following records shall be retained for at least five years:
Records and logs of unit operation covering time interval at each a.
power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety, c.
All REPORTABLE EVENTS submitted to the Commission, d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
Records of changes made to the procedures required by Specification e.
6.8.1.
f.
Records of radioactive shipments.
Records of sealed source and fission detector leak tests and results.
g.
h.
Records of annual physical inventory of all sealed source material of record.
SEQUOYAH - UNIT 1 6-22 Amendment Nos. 52, 58, 74, 117, 178
F ADMINISTRATIVE CONTR0l.S 7The following records shall be retained for the duration of the Unit 6.10.2
- Operating License:
a.
Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of radiation exposure for all individuals entering radiation control areas.
d.
Records of gaseous and liquid radioactive material released to the environs and the resulting calculated dose to an individual member of the public, e.
Records of transient or operational cycles for those unit components identified in Table 5.7-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the facility staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required for lifetime reten-tion by the Nuclear Quality Assurance Plan, j.
Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PORC and the NSRB.
l 1.
Records of analyses required by the radiological environmental monitoring program.
m.
Records of secondary water sampling and water quality.
n.
Records of the service life monitoring of all safety-related hydraulic and mechanical snubbers, required by T/S 3.7.9, including the maintenance performed to renew the service life.
i o.
Records for Environmental Qualification which are covered under the provisions of Paragraph 2.c.(12)(b) of License No. DPR-77.
p.
Records of reviews performed for changes made to the 0FFSITE DOSE CALCULATION tiANUAL and the PROCESS CONTROL PROGRAM.
Y SEQUOYAH - UNIT 1 6-23 Amendment Nos. 42, 58,-74, 148, 163, 174, 178
ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall_be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601(a) of 10 CFR 20, each'high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be bar-ricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit * (RWP).
Any individual or group of individuals permitted to enter such areas shall be provided with er accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset. integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has.been established and personnel have been made knowledgeable of them, c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This indi-vidual shall be responsible for providing positive control over the activities within the area and shall perform control over the activi-ties within the area and shall perform' periodic radiation surveil-lance at the frequency specified by the facility Site Radiological Control Manager in the RWP.
6.12.2 The requirements of 6.12.1, above, shall also apply to each high radia-tion area in which the intensity of radiation is greater than~1000 mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Operations Supervisor on duty and/or the' Site Radiological Control l
- Manager,
- Radiological Control personnel or personnel escorted by Radiological Control personnel in accordance with approved emergency ' procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided_they comply with approved radiation protection procedures for entry inte high radiation areas.
SEQUOYAH - UNIT 1 6-24 Amendment Nos. 42, 58, 74, 148, 152, 174, 178-
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 Changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.p.
This documentation shall contain:
sufficient information to support the change together with the a.
appropriate analyses or evaluations justifying the change (s) and b.
a determination that the change will naintain the overall con-formance of the solidified waste product to existing require-ments of Federal, State, or other applicable regulations.
2.
Shall become effective after review and approval in accordance with Section 6.5 lA.
6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 Changes to the ODCM:
l.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.p.
This documentation shall contain:
Sufficient information to support the change together with the a.
appropriate analyses or evaluations justifying the change (s) and b.
A determination that the change will maintain the-level of radioactive effluent control pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part.50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
2.
Shall become effective after review and acceptance by the process in Specification 6.5.1A and the SQN PORC.
3.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified by markings.in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
i e
l.I SEQUOYAH - UNIT 1 6-25 Amendment Nos. 42, 58, 74, 148,-169, 174,1178 3
,,. ' ta va
.,g i
9 UNITED STATES ij NUCLEAR REGULATORY COMMISSION Y,
[
WASHINGTON, D,C. 20555-0001 TENNESSEE VALLEY AUTHORITY 00GET NO. 50-328 SE0VOYAH NUCLEAR PLANT. UNIT _2 AMENDMENT TO FACILITY OPERATING LICENSI Amendment No. 169 License No. DPR-79 2
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 7, 1993, 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.
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 assuranco (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.
-i i
.um. &c:a m s, w
.,+m
. 2.
Also, License Condition 2.C.(16)a. of Facility Operating License 79 is hereby amended to read as follows:
TVA shall provide a fully-trained on-shift technical advisor to the shift operations supervisor.
3.
Also, the license is amended by changes to the Technical Specifications as indicated in Attachment 2 to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR 79 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 169, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
4.
This license amendment is effective as of its date of issuance, to be implemented within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
[
Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachme1t:
1.
Page 6 of License
- 2.
Changes to the Technical Specifications Date of Issuance: thrch 31,1994 Page 6 is attached for convenience, for the composite license to reflect this change.
- A re
- 2.
me <. ns.
m
l l
l 6-(13)
Fire Protection system (Section 9.5) a.
TVA shall maintain in effect and fully implement all provi-sions of the approved fire protection plan and the NRC staff's Fire Protection Review in the Sequoyah Safety Evaluation Re-port and Supplements.
b.
TVA shall replace the control room ceiling panels with panels i
acceptable to NRC by September 30, 1981.
j c.
TVA shall comply with Section III.G, III.J, III.L and III.0 of Appendix R of 10 CFR 50, except where NRC has approved devia-tions, on a schedule consistent with that required for other operating re w. tors.
By October 1,1981, TVA shall submit a report that identifies and justifies differences between existing or proposed fire protection feicures and those fea-tures specified in Section III.G, III.J, III.L and III.0 of Appendix R to 10 CFR Part 50.
(14)
Comoliance With Reaulatory Guide 1.97 TVA shall implement modifications necessary to comply with Revi-sion 2 of-Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," dated December 1980 by startup from the Unit 2 Cycle 4 refueling outage.
(15)
Corrosion of Carbon Steel Pioina TVA shall carry out a surveillance program on corrosion of carbon steel piping in accordance with TVA document SQRD-50-328/81-10 dated August 25, 1981, and procedures for implementation are to be submitted for NRC concurrence by October 15, 1981.
(16)
NUREG-0737 Conditions (Section 22.2)
Each of the following conditions shall also be performed to the satisfaction of the NRC:
a.
Shift Technical Advisor (Section 22.2. I.A.1.1)
TVA shall provide a fully-trained on-shift technical advisor to the shift operations supervisor, b.
Indeoendent Safety Enaineerina Group (Section 22.2. I.B.1.2)
TVA shall have an onsite Independent Safety Engineering Group.
Amendment No. 45,169
-l l
ATTACHMENT 2 TO LICENSE AMENDMENT NO.160 j
FACILITY OPERATING LICENSE NO. DPR-79 l
DOCKET NO. 50-328
~
Revise the Appendix A Technical' Specifications by removing.the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain' marginal lines indicating the area of change.
EftLOVE INSERT Index page XVIII Index page XVIII 1-4 1-4 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-4 6-5 6-5 6-6 6-6 6-8 6-8 6-10 6-10 6-11 6-11 6-12 6-12 6-13 6-13 6-15 6-15 6-16 6-16 6-23 6-23 6-24 6-24 6-25 6-25 6 6-26 1;.
67 JM -
h l
J..
INDEX
.n K
ADMINISTRATIVE CONTROLS q
SECTION EASE Meeting Frequency..............................................-
6-10 Quorum.........................................................
6-10 Review.........................................................
6-10=
i Audits......................................................
6-11 1,
i
. Authority......................................................
6-12.'
Records........................................................
6-12'-
E 6.3 DELETED 1 6.6 REPORTABLE EVENT ACTI0N.......................................... 14
- 6.7 SAFETY LIMIT VIOLATION...........................................
.6-14
' 6.8 PROCEDURES AND PR0 GRAMS..........................................
6-14:
6.9 REPORTING' REQUIREMENTS 6.9.1 ROUTINE REPb9TS)............................................... 17k 6.9.2 SPECIAL REP 0R'IS................................................-
6-21 f
= 6.10 RECORD RETENTION................................................
6-22 6.11 RADIATION PROTECTION PR0 GRAM....................................
6 -
41-i LSEQUOYAH - UNIT 2 XVIII Amendment No. 50, 66, 1691 k
~
. ~.. -
i DEFINITIONS IDENTIFIED LEAKAGE 1.16 IDENTIFIED LEAKAGE shall be:
j a.
Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump.
oc collecting tank, or b.
Leakage into th' containment' atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE B0VHDARY LEAKAGE, or c.
Reactor coolant system leakage through a steam generator to the secondary system.
MEMBER (S) 0F THE PUBLIC 1.17 MEMBER OF THE PUBLIC means an individual in a controlled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose.
OFFSITE DOSE CALCULATION MANUAL 1.18 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiologi-cal Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitcring Pro-grams required by Section 6.8.4 and (2) descriptions of the'information that l-should be. included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.6-and 6.9.1.8.
OPERABLE - OPERABILITY 1.19 A system, subsystem, train, or component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, a normal and an emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, com-ponent or device to perform its function (s) are also capable of performing their related support function (s).
SEQUOYAH - UNIT 2 1-4 Amendment No. 63,.134, 146, 159, 165, 169 h
4 d
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Shift Operations Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room com-mand function. A management directive to this effect, signed by the Site Vice President shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS An onsite and an.offsite organizativ shall be established for unit operation and corporate management. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be estab-lished and defined from the highest management levels through-inter-mediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key: personnel positions, or.in equivalent forms of documentation.-
These' requirements shall be documented in the FSAR and will be updated in accordance with 10 CFR 50.71(e),
b.
The Senior Vice President, Nuclear Power shall have corporate respon-
'l-sibility for overall plant nuclear safety. This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical-support in the plant so that continued nuclear safety is assured.
c.
The Plant Manager shall be responsible for overall unit safe opera-tion, and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 FACILITY STAFF a.
Each on duty unit shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Reactor Operator shall be in the unit Control Room when fuel is in the reactor.
In addition, while the unit is~in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.
SEQUOYAH - UNIT 2 6-1 Amendment No. 24, 50, 66, 142, 169
o ADMINISTRATIVE CONTROLS A Radiological Control technician # shall be onsite when fuel is in' the c.
m reactor.
t d.
All CORE ALTERATIONS _shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to a
Fuel Handling who has no other concurrent responsibilities durin'g this operation.
A Fire Brigade of at least 5 members shall be maintained onsite at all e.
times #.
The Fire Brigade shall not include the Shift Operations Super-(
visor and 2 other members of the minimum shift crew necessary for safe-shutdown of the unit or.any personnel required for other essential functions during a fire emergency.
f.
The Operations Superintendent shall hold a Senior Reactor Operator license.
g.
Administrative procedures shall be developed and implemented to limit-the working hours of unit staff who perform safety-related functions (i.e., senior reactor operators, reactor operators, assistant unit operators, Radiological Control, 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 unit is operating. However, in the event that unforseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refuel-ing, major maintanance, or major plant modification, on a temporary basis the following guidelines shall be followed:
1.
An individual should not be permitted to work more than 16' hours 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 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 in advance by the Plant Manager or his designee, in accordance with approved administrative procedures, or by 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 Plant Manager or his designee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
- The Radiological Control technician 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.
SECUDYAH - UNIT 2 6-2 Amendment.No. 50, 66, 142, 14%'169-i
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION WITH UNIT 1 IN MODE 5 OR 6 OR DE-FUELED
' Position Number of individuals required to fill position Modes 1, 2, 3, & 4 Modes 5 & 6 SOS l'
l' l
SRO 1
None R0 2
1 6
A0 2
2 STA 1
None WITH UNIT 1 IN MODES 1, 2, 3, or 4 Postion Number of individuals required to fill position Modes 1, 2, 3, & 4 Modes 5 & 6 SOS l'
l' l-SR0 l'
None b
R0 2
3 6
A0 2
1 STA 1*
None A/
Individual may fill. the same position on Unit 1.
h/
One of the two required individuals may fill the same position on Unit 1.
4 SEQUOYAH.- UNIT 2 6-3 Amendment No. 50, 66, 169-
I c
TABLE 6.2-1 (Continuedl TABLE NOTATION SOS -
Shift Operations Supervisor with a Senior Reactor Operators License l
on Unit 2 SR0 -
Individual with a Senior Reactor Operators License on Unit 2 R0 Individual with a Reactor Operators License on. Unit 2 A0 Auxiliary Operator STA -
Shift Technical Advisor Except for the Shift Operations Supervisor, the Shift Crew Composition may be l
one less than the minimum requirements of Table 6.2-1 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 of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Com-position to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Operations Supervisor from the Control Room l
while the unit is in MODES 1, 2, 3 or 4, an individual (other than the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room command function.
During an absence of the Shift Operations
.l Supervisor from the Control Room while the unit is in MODE 5 or 6, an indi-vidual with a valid SR0 or R0 license (other than the Shift Technical Advisor) shall be designated to assume the Control Room command function.
SEQUOYAH - UNIT 2 6-4 Amendment No. 50, 66, 169
-(
i ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING (ISE)
FUNCTION 6.2.3.1 The ISE shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The.ISE shall' be composed of at least 3 dedicated ' full-time engineers.
located onsite. These engineers will be supplemented as necessary by full-time engineers shared among all TVA nuclear sites to achieve an equivalent staffing of 5 full-time engineers performing the ISE functions applicable to Sequoyah.
RESPONSIBILITIES 6.2.3.3 The ISE shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that'these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 The ISE shall make detailed recommendations for revised procedures',
equipment modifications, or other means of improving plant safety to the Manager, Nuclear Experience. Review / Independent Safety. Engineering.
5.2.4 SHIFT TECHNICAL ADVISOR (STA) 6.2.4.1 The STA shall serve in' an advisory capacity to the Shift Operations l
Supervisor on matters pertaining to the' engineering aspects of assuring safe operation of the unit.
b.3 FACILITY STAFF OVALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions except for the Site Radiological Control Manager who shall meet or exceed the qualifications of-Regulatory' Guide 1.8, September 1975.
4
- Not responsible for sign-off function.
SEQUOYAH - UNIT 2 6-5 Amendment No. 50, 66, 108, 142, 151 169
ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under_the direction of the Plant Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55 and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.0 Senior Vice President, Nuclear Power is responsible for the safe-opera-tion of all TVA power plants.
6.5.1 ' PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.l' The PORC shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The PORC shall be composed of the:
Chairman:
Plant Manager Member:
Operations Manager Member:
Radiological and Chemistry Manager l.
Member:
Maintenance Manager Member:
Technical Support Manager Member:
Quality Audit and Assessment Manager Member:
Site Engineering Representative i
~
SEQUOYAH - UNIT 2 6-6 Amendment No. 55,66,142 153, 169 l
1
n
. ADMINISTRATIVE CONTROLS
'i.
Review of every unplanned.onsite release of radioactive-material to.
-the environs including the preparation and forwarding of reports-covering evaluation', recommendations and disposition of the correc-tive action to prevent. recurrence to the Site Vice President.and to the Nuclear Safety Review Board.
j.
Review of all proposed changes to the OFFSITE DOSE CALCULATION MANUAL.
AUTHORITY 6.5.1.7 The PORC shall:
Recommend in writing to the Plant Manager approval or disapproval of a.
items considered under 6.5.1.6(a), (b) and (c)~above, b.
Require a determination in writing with regard to whether or not each item considered under 6.5.1.6(b), (c), and (e) above constitutes an unreviewed safety question.
c.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Site Vice Presi--
dent and the Nuclear Safety Review Board of disagreement between the PORC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The PORC shall maintain written minutes of each PORC meeting that, at a minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these technical specifications.
Copies shall be provided to the Site Vice President and the Nuclear Safety Review Board.
6.5.1A TECHNICAL REVIEW AND CON 1R01 ACTIVITIES 6.5.1A.1. Activities which affect nuclear safety.shall be conducted as follows:
Procedures required by Specification 6.8.1 and other procedures which a.
affect plant nuclear safety, and changes thereto, 'shall be prepared,-
reviewed and approved.
Each such procedure or procedure change shall.
be reviewed by a qualified individual other than the individual who
. prepared the procedure or procedure change, but who may be-from the same organization as the individual who prepared the procedure or procedure change.
Procedures shall be approved by the appropriate responsible manager as designated in writing by the Plant Manager.
The Plant Manager, or Duty Plant Manager shall approve designated Administrative Procedures.
b.
Proposed changes or modifications to structures, systems, and compo-nents~ that affect plant nuclear safety shall be reviewed by.a quali-fied individual / group other than the individual / group which designed the modification, but who may be from the same organization SEQUOYAH --UNIT 2 6-8 Amendment No.. 50, 66, 142, 169
ADMINISTRATIVE CONTROLS CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRB Chairman to provide expert advice to the NSRB.
MEETING FRE0VENCY 6.5.2.5 The NSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per six months thereafter.
000RUJ 6.5.2.6 The' minimum quorum of the NSRB necessary for the performance of the NSRB review and audit functions of these technical specifications shall consist of more than half the NSRB membership or at least 5 members, whichever is greater.
This quorum shall include the Chairman or his appointed alternate and the NSRB members, including appointed alternate members, meeting the require-ments of Specification 6.5.2.3.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
RFJ_LG 6.5.2.7 The NSRB shall be cognizant of review of:
a.
The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions' did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59,10 CFR.
c.
Proposed tests or experiments which involve an unreviewed safety H
question as defined in Section 50.59, 10 CFR~
1 d.
Proposed changes to Technical Specifications or this Operating License.
j e.
Violations of codes, regulations, orders, Technical Specifications -
license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety.
g.
All REPORTABLE EVENTS.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
1 1.
Reports and meetings minutes of the PORC.
[
SEQUOYAH - UNIT 2 6-10 Amendment No. 50, 66, 169-
ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance.of the NSRB. These audits shall encompass:
a.
The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.
D b.
The performance, training and qualifications of the entire facility' staff at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months, d.
The performance of activities required by the Nuclear Quality Assur-l ance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
e.
The Site Radiological Emergency Plan and implementing procedures at least once per 12 months.
f.
' The Plant Physical Security Plan, the Safeguards Contingency Plan, and implementing procedures at least once' per 12 months.
g.
Any other area of unit operation considered appropriate by the NSRB:
or the Senior Vice President, Nuclear Power.
h.
The Facility Fire Protection Program and implementing procedures at' least once per 24 months.
i.
An independent fire protection and loss prevention program inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
j.
An inspection and audit of the fire-protection and loss prevention-program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
k.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
1.
The 0FFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
m.
The PROCESS CONTROL PROGRAM and implementing proceoures for.
SOLIDIFICATION of radioactive wastes at.least once per 24-months.-
n.
The performance of activities required by the Quality Assurance Pro-gram to meet the criteria of Regulatory Guide'4.15,' December 1977 or Regulatory Guide 1.21, Rev. I',1974 and Regulatory Guide 4.1, Rev.1, 1975, at least once per 12 months.
SEQUOYAH - UNIT 2 6-11 Amendment No. 34, 60,.66, 169
s ADMINISTRATIVE CONTROLS AUTHORITY 6.5.2.9 The NSRB shall report to and advise the Senior Vice President, Nuclear Power on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS l
6.5.2.10 Records of NSRB activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each NSRB meeting shall be prepared, approved and-forwarded to the Senior Vice President, Nuclear Power within 14 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Senior Vice President, Nuclear Power within 14 days following completion of the review.
c.
Audit reports encompassea by Section 6.5.2.8 above, shall be for-warded to the Senior Vice President, Nuclear Power and to the manage-ment positions responsible for the areas audited within 30 days after completion of the audit.
6.5.3 THIS SPECIFICATION IS DELETED
.)
i ll SEQUOYAH - UNIT 2 6-12 Amendment No. 50, 66,.142, 169.
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- SEQUOYAH.'-. UNIT.' 2 -
6-13 Amendment No.- 50, 66, 142, 169
+
-ADMINISTRATIVE CONTROLS h,
Quality Assurance Program for effluent and environmental monitoring,.
l~
using the guidance contained in Regulatory Guide 4.15, December 1977 or Regulatory Guide 1.21, Rev.1,1974 and Regulatory Guide 4.1, Rev.
1, 1975.
1.
OFFSITE DOSE CALCULATION MANUAL implementation.
. l'
~6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed and approved prior to implementation as set forth'in Specification 6.5.1A above.
6.8.3 Temporary changes to procedures of 6.8.1 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.
The change is approved in accordance with Specification 6.5.1A above c.
within 14 days of_ implementation.
6.8.4 The following programs shall be established, implemented, maintained, and changes thereto made in accordance with Section 6.5.lA:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those' portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the safety injection system, residual _ heat removal system, _ chemical and volume control system, containment spray system, and RCS sampling system. The program shall-include the following:
(i) Preventive maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.
SEQUOYA1 - UNIT 2 6-15 Amendment No. 34, 50, 66, 134,169 r
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< e ADMINISTRATIVE CONTROLS
~
- b.
In-Plant Radiation Monitorina
~
A program which will? ensure the' capability to accurately determine the airborne _ iodine concentrations in vital areas;under accident conditions. This program shall include the.following:
(1) _ Training of personnel, (ii) Procedures for monitoring, and!
(iii)
Provisions for maintenance of sampling and analysis equipment..
c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibiti steam generator tube degradation. This program shall-include:
(i)
Identification of a sampling schedule for. the critical variables and control points for these variables, (ii)
Identification of the procedures used to measure the values of:
the critical variables, (iii)
Identification of process' sampling. points,'whichLshall include monitoring the discharge of the condensate pumps for evidence of condenserfin-leakage,.
(iv) Procedures for the recording and management of_ data,-
(v)
Procedures defining corrective actions for off-control point chemistry conditions, (vi)_ Procedures identifying (a) the authority responsible for the interpretation of the data; and (b) the sequence'and timing of-administrative events required to initiate corrective action.
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s d.
Deleted 1
i
- SEQUOYAH --UNIT 2.
6-16 Amendment No. 50, 66, 149, 169
ADMINISTRATIVE CONTROLS
- r
-Diesel Generator Reliability Imorovement Proaram (Continued)
A supplemental report sh'all be~ prepared within 30 days after each subsequent failure during a valid demand for so long as the affected diesel generator unit continues to' violate the criteria (3/20 or 6/100) for the reliability improve-ment program remedial action. The supplemental report need only update the failure / demand history for the affected diesel generator unit since the last' report for that diesel generator. The supplemental report shall also present an analysis of the failure (s) with a root cause determination, if possible, and shall delineate any further procedural, hardware or operational.. changes to be incorporated into the diesel generator improvement program and the schedule.for implementation of those changes.
In addition to the above, submit a yearly data report on the diesel generator reliability.
6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained -for at least the minimum period indicated.
6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of unit operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTABLE EVENTS submitted to the Commission.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications, e.
Records of changes made to the procedures required by Specification 6.8.1.
l.
f.
Records of radioactive shipments.
g..
Records of sealed source and fission detector leak tests and results.
h.
Records of annual physical inventory of all sealed source material of:
record.
SEQUOYAh UNIT-2 6-23 Amendment No. 44, 50, 56, 107,.134, 169 1
ADMINISTRATIVE CONTROLS 1,
L6.10.2 The following records shall be retained for the duration of the Unit Operating License:
a.
Records and drawing changes reflecting unit design modifications made to. systems and equipment described in the Final Safety Analysis.
Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories, c.
Records of radiation exposure for all individuals entering radiation control areas.
d.
Records of gaseous and liquid radioactive material released to the environs and the resulting calculated dose to an individual member of the publi_c.
e.
Records of transient or operational cycles for those unit components identified in Table 5.7-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current members of the facility staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities required for lifetime reten-tion by the Nuclear Quality Assurance Plan.
J.
Records of reviews performed for changes made to procedures or equip--
ment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the PORC and the NSRB.
J.
1.
Records of analyses required by the radiological environmental monitoring program.
m.
Records of secondary water sampling and water quality.
n.
Records of. the service life monitoring of all safety-related-hydrau-lic and mechanical snubbers, required by T/S 3.7.9, including the maintenance performed to renew the service life.
o.
Records for environmental qualification which are covered under the provisions of paragraph 2.C.(10)(b) of license No. DPR-79.
p.
Records of reviews performed for changes made to the OFFSITE DOSE j
CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
SEQUOYAH - UNIT 2 6-24 Amendment No. 28, 50, 66,.
)
134,'153, 165,169
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o s
ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM
~
Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601(a) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be bar-ricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit * (RWP).
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the' area has been estab-
'lished and personnel have been made knowledgeable of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This indi-vidual shall be responsible for providing positive control over the activities within the area and shall perform control over the activ-ities within the area and shall perform periodic radiation surveil-lance at the frequency specified by the facility Site Radiological Control Manager in the RWP.
6.12.2 The requirements of 6.12.1, above, shall also apply to each high radia-tion area in which the intensity of radiation is greater than 1000 mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Operations Supervisor on duty and/or the Site Radiological Control
[
Manager.
- Radiological Control personnel or personnel escorted by Radiological Control personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation' areas.
SEQUOYAH - UNIT 2 6-25 Amendment No. 34, 50, 66, 134, 142,.165,169
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1 ADMINISTRATIVE CONTROLS l
i 5.13 PROCESS CONTROL PROGRAM (PCP)
]
1 I
6.13.1 Changes to the PCP:
l L-1.
Shall be documented and records of reviews performed shall be d
L retained as required by Specification 6.10.2p.
This documentation i
shall contain:
j a.
Sufficient information-to support the change together with the-appropriate analyses or evaluations justifying the change (s) and-b.
A determination that the change will. maintain the overall con-
)
formance of the-solidified waste product to existing require-I ments of Federal, State, or other applicable regulations.
)
2.
Shall become effective after review and approval in accordance with 3
Section 6.5.1A.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) j i
6.14.1 Changes to the ODCM:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2p. This documentation shall'contain:
a.
Sufficient information to support the change.together with the appropriate analyses or evaluations justifying the change (s) and b.
A determination that the change will maintain the level.of radioactive effluent control pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a,.and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
2.
Shall become effective after review and acceptance by the process in Specification 6.5.1A and the SQN PORC.
3.
Shall be submitted to the Commission in the form of a' complete, legible copy of the entire ODCM as a part of or concurrent'with the.
Annual Radioactive Effluent Release Report for the period of the repert in which any change to the ODCM was made.. Each ' change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
SEQUOYAH - UNIT 2 6-26 Amendment No. 34, 50, 66, 134, 159, 165 169
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