ML20082M120
| ML20082M120 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-77-A-032, DPR-77-A-32, DPR-79-A-024, DPR-79-A-24) |
| Issue date: | 11/10/1983 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082M123 | List: |
| References | |
| NUDOCS 8312050714 | |
| Download: ML20082M120 (12) | |
Text
y.m'c UNITED STATES
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NUCLEAR REGULATORY COMMISSION q
i WASHINGTON, D. C. 2uS55 TEIMISSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated March 15 and March 16, 1983, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's reou-lations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the-rules and regulations of the Com-mission; 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 conpliance 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.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A-Technical Specifications as indicated-in the attachment to this license amend-ment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 32, are hereby incorporated into the license.-
8312050714 831110 PDR ADOCK 05000327 P
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2-The licensee shall; operate the facility in accordance with the Technical Specificetions.
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4 This license amendment is effective as of its date of issuence.
3.
FOR THE' NUCLEAR REGULATORY CO MISSION
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ch Elinor G. Adensam, Chief'.
Licensing Branch No. 4.
Division >>f Licensing
Attachment:
Appendix A Technicel Specification Changes Date of Issuance: November 10, 1983 p
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ATTACHMENT TO LICENSE f.MENDPENT NO. 32 FACILITY OPERATING LICENSE NO. DPR-77 00CKFT NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the' areas of change.
Acended Page 6-1 6-12 3/4 7-35 1
O I
4 1
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6.0 ADMINISTRATIVE CONTROLS f
6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Chief, Radiological Hygiene Branch, shall be responsible for imple-menting the radiological environmental program and dose calculations and projections as described in the Offsite Dose Calculation Manual. (ODCM).
These responsibilities include performance of surveillance requirements listed in Table 6.1-1.
6.1. 3 The Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command function.
A management directive to this effect, signed by the NUC PR Division Director, shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION OFFSITE 6.2.1.1 The offsite organization for unit manacement and technical support shall be as shown in Figure 6.2-1.
6.2.1.2 The offsite organization for the radiological environmental monitor-ing program and dose calculations shall be as shown in Figure 6.2-3.
l UNIT STAFF i
6.2.2 The Unit organization shall be as shown in Figure 6.2-2 and:
a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
l b.
At least one licensed Reactor Operator shall be in the Control Room 3
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.
I SEQUOYAH - UNIT 1
_6-1 Amendment No. 32-
3 ADMINISTRATIVE CONTROLS The Site Radiological Emergency Plan and implementing procedures at e.
j least once per 12 months.
}
f.
The Plant Physical Security Plan, the Safeguards Contingency Plan, and implementing procedures at least once per 12 months.
i g.
Any other area of unit operation considered appropriate by the NSR8 or the Manager of Power.
i h.
The' Facility Fire Protection Program and implementing procedures at-least once per 24 months.
1.
An independent fire protection and loss prevention program inspection.
and audit shall be performed annually otilizing either qualified offsite licensee personnel or an outside fire protection firm.
i 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.
i 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.
The PROCESS CONTROL ~ PROGRAM and implementing procedures for m.
SOLIDIFICATION of radioactive wastes at least once per 24 months.
The performance of activities required by the Quality Assurance n.
Program to meet the criteria of Regulatory Guide 4.15, December 1977 -
J at least once per 12 months.
AUTHORITY I
6.5.2.9-The'NSRB shall report to and advise the Manager of Power on those.
areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8; 4
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 'txt prepared, approved and forwarded.
to the Manager of Power within 14 days following'each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 a ove, shall.be prepared, approved and forwarded to the Manager of fower.within 14 days following completion of;the review.
a SEQUOYAH - UNIT 1:
6-12 Amendment No.1321 a
PLANT SYSTEMS C_O, SYSTEMS
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LIMITING CONDITION FOR OPERATION 3.7.11.3 The following low pressure CO systems shall be OPERABLE.
2 a.
Computer Room.
b.
Auxiliary Instrument Room.
c.
Diesel Generator Rooms.
d.
Fuel Oil Pump Rooms.
APPLICABILITY:
Whenever equipment protected by the CO systems is required to 2
be OPERABLE.
ACTION:
a.
With one or more of the above required CO2 systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.
Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.11.3.1 Each of_the above required CO systems shall be demonst' rated j
2 OPERABLE at least once per 31 days by verifying that each valve (manual', power.
operated or automatic) in the flow path is in its correct position.
,i 4
4 SEQUOYAH - UNIT 1 3/4 7-35 Amendment No.32:
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g NUCLEAR REGULATORY COMMISSION
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,t WASHINGTON, D. C. 20$$5 a
%, *.... f TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE0V0YAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The applications for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated March 15 and March 16, 1983, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regu-lations as set forth in 10 CFP Chapter I; B.
The facility will operate in confornity with the license, as amended, the provisions of the Act, and the rules and regulations of the. Con-mission; 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.comon 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 Comission's regulations and all applicable requirements nave been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amend-nent and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications lhe Technical Specifications contained in Appendix A, as revised-through Anendment No.24, are hereby incorporated into the license.
4 L..
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The licensee shall operate the fecility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
{
M Elinor G. Adensam, Chief Licensing Branch No. 4 Divisfon of Licensing
Attachment:
Appendix A Technical Specification Changes Date of Issuance: November 10, 1983 v
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L ATTACH 11ENT TO LICENSE AMENDMENT NO. 24 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET N0. 50-328 f
Replace the following peges of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertice1 lines indicating the areas of change.
Amended
~
Page 6-1 t
6-15 3/4 7-47
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4 m.
ADMINISTRATIVE CONTROLS The Site Radiological Emergency Plan and implementing procedures at l
e.
1 east once per 12 months.
l I
f.
The Plant Physical Security Plan, the Safeguards Contingency Plan, and implementing procedures at least onch per 12 months.
g.
Any other area of unit operation considered appropriate by the NSRB or the Manager of 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 inspectica and audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection fir *m.
j.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant l
,at intervals no greater than 3 years, j
l 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.
The PROCESS CONTROL PROGRAM and implementing procedures for m.
SOLIDIFICATION of radioactive wastes at least once per 24 months.
n.
The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, December 1977 at least once per 12 months.
AUTHORITY 6.5.2.s lhe NSRB shall report to and advise the Manager of Power on 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 Manager of Power within 14 days following each meeting, b.
Reports of reviews encompassed by Section 6.5.2.? above, shall tHe prepared, approved and forwarded to the Manager of Power within i
14 days following completion of the review.
v.
. 24' SEQUOYAH - UNIT 2
.6-15 AMENDMENT NO.
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
6.1.2 The Chief, Radiological Hygiene Branch, shall be responsible for implementing the radiological en.vironmental program and dose calculations and projections as described in the Offsite Dose Calculation Manual (ODCM).
These responsibilities include performance of surveillance requirements listed in Table 6.1-1.
6.1.3 The Shift Supervisor (or during his absence from the Control Room, a designated individual) shall be responsible for the Control Room command func-tion.
A management directive to this effect, signed by the NUC PR Division Director, shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION OFFSITE 6.2.1.1 The offsite organization for unit management and technical support-shall be as shown on Figure 6.2-1.
6.2.1.2 The offsite organization for the radiological enviromental monitoring program and dose calculations shall be as shown in Figure 6.2-3.
UNIT STAFF 6.2.2 The Unit organization shall be as shown on Figure 6.2-2 and:
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 Reactor Operator shall be in the 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.
i 24 SEQUOYAH - UNIT 2 6-1 AMENDMENT NO.
PLANT SYSTEMS CO SYSTEMS 2
LIMITING CONDITION FOR OPERATION 3.7.11.3 The following low prassure CO systems shall be OPERABLE.
2 a.
Computer Room b.
Auxiliary Instrument Room c.
Diesel Generator Rooms d.
Fuel Oil Pump Rooms APPLICABILITY:
Whenever equipment protected by the CO systems is required to 2
be OPERABLE.
ACTION:
With one or more of the above required CO, systems inoperable, a.
within one hour estabitsh a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged, for other areas, establish an nourly fire watch patrol.
Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action teken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.11.3.1 Each of the above required C0 systems shall be demonstrated 7
OPERABLE at least once per 31 days by verTfying that each valve (manual, power operated or automatic) in the flow path is in its correct position.
4.7.11.3.2 Each of the above required low pressure CO systems shall be demonstrated OPERABLE:
2 At least once per 7 days by verifying the'C0 ' storage tank' level to a.
9 be greater than 50% and pressure to be greater than 270 psig, and b.
At least once per 18 months by verifying:
1.
The system valves and associated ventilation d?.mpers and fire door release mechanisms actuate manually and automatically, upon receipt of a simulated actuation signal, and 2.
Flow from each nozzle during a " Puff Test."
SEQUOYAH - UNIT 2 3/4 7 Amendment.No. 24