ML20099H981
| ML20099H981 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/13/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099H984 | List: |
| References | |
| TAC-55029, TAC-55030, NUDOCS 8411280412 | |
| Download: ML20099H981 (18) | |
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- pare:o UNITED STATES
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NUCLEAR REGULATORY COMMISSION L
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ALABAMA POWER COMPANY hl
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JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 1 DOCKET NO. 50-348 AMENDMENT TO FACILITY OPERATING LICENSE Q
I Amendment No. 53 License No. NPF-2 1.
The Nuclear Regulatory Comission (the Comission) has found that:
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A.
The application for amendment by Alabama Power Company (the
~
i licensee)datedMay 14, 1984, complies with the. standards and j
requirements of the Atomic Energy Act of 1954, as amended (the
' Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.-Re-facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (i)thattheactivitiesauthorizedby 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 Comission's regulations; f
D.
The issuance of this license 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical s
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-2 is hereby r
j amended to read as follows:
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-j (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 53, are
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i hereby incorporated in the license. The licensee c,
shall operate the facility in accordance with the A
Technical Speciffcations.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 3;
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Ij Steven A. Varga, Chief y
Operating Reactors Branch #1
,j Division of Licensing
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Attachment:
Changes __to the Technical 2
Specificat4ons Date of Issuance: November 13, 1984 G
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j ATTACHMENT TO LICENSE AMEN 0 MENT NO. 53 j
AMENDMENT NO. 53 FACILITY OPERATING LICENSE NO. NPF-2 j.
DOCKET NO. 50-348 i
Revised A pendii A as follows:
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6.1 RESPONSIBILITY l
6.1.1 The Plant Manager shall be responsible for overall unit ' operation and sha.11 delegate in writing the succession to this responsibility during his absence.
t 6.1.2 The Shift Supervisor or during his absence from the Control Room a
,4' designated individual shall be responsible for the Control Room Command function. A management directive to this effect, signed by the Senior V.fce President responsible for Nuclear Generation, hereafter referred to as i
i Senior Vice President, shall be reissued on an annual basis.
i 6.2 ORGANIZATION 1
OFFSITE
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6.2.1 The offsite organization for facility management and technical 1
support shall be as shown on Figure 6.2-1.
FACILITY STAFF
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6.2.2 Tyacility organization shall be as shown on Figure 6.2-2 and-l.
a.
E.nch on-duty shift shall be composed of at least the minimum
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shift crew composition shown in Table J.2-1.
b.
At least one licensed Reactor Operator s'ha11 be"in the control room when fuel is in the reactor. In a.ddition, at least one 4
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licensed Senior Reactor Operator shall be in the Control Room j
while the unit is in MODE 1, 2, 3 or 4.
fj c.
A health physics technician f shall be on site when fuel is in the reactor.
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d.
ALL CORE ALTERATIONS shall be 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.
q e.
A site Fire Brigade of at least 5 members shall be maintained j
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onsite at all times.# The Fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shutdown of U
the unit and any personnel required for other essential functions during a fire emergency.
O N
GThe health physics 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 d
to accomodate unexpected absence of the health physics technician and/or 1
Fire Brigade members provided imediate action is taken to restore the fl health physics technician and/or Fire Brigade to within the minimum ll requirements.
1 FARLEY-UNIT 1 6-1 AMEN 0 MENT NO. 53 l-
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Executive il Lj Vice President j) i i
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Manager Manager Plant Manager Manager Safety Audit and Nuclear Operation; Farley Nuclear Engineering i
Engineering Review and Administration
& Technical Support
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Supervisor Staff Plant Staff l
Safety Audit and l
Staff Engineering Review i
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Ci Figure 6.2-1 Offsite Organization for Facility Management and Technical Support it i
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ADMINISTRATIVE CONTROLS
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i 6.2.3 SAFETY AUDIT AND ENGINEERING REVIEW GROUP (SAERG)
L FUNCTION 6.2'.3.1 The SAERG shall function to conduct operational evaluations,
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engineering 'revfews, and audits for the purpose of improving safety.
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6.2.3.2 The SAERG shall be composed of multi-disciplined dedicated onsite group with a minimum assigned complement of five engineers or appropriate ll specialists.
RESPONSIBILITIES 6.2.3.3 The SAERG shall be responsible for the following:
a.
Participating in operational evaluations for improvement of safety wherein such evaluations and recommendations therefrom are not limited to the fulfillment of existing programs, policies, procedures, or capabilities of existing equipment and
_inJta11ations.
b.
Systematic engineering reviews of plant perfomance and activities with results reported independently of onsite operational management to offsite upper management.
c.
Comprehensive plant audits in accordance.with audit requirements i
set forth in quality assurance programs, ifcensing documents, and other policies and procedures.
AUTHORITY
- 6.2.3.4 The onsite SAERG shall carry out its function reporting offsite directly to the Manager-Safety Audit and Engineering Review who in turn reports directly to the Senior Vice President.
l 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to l
the Shift Supervisor primarily in the assessment of accident and transient Ij occurrences.
6.3 FACILITY STAFF QUALIFICATIONS
'1
- 'i 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of l
the March 28, 1980 NRC letter to all licensees, except for (1) the Health l
Physics Supervisor who shall meet or exceed the qualifications of Regulatory l
Guide 1.8, September 1975.
FARLEY-UNIT 1 6-6 AMENDMENT NO. 53 l
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ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The PORC shall:
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' a.
Recommend to the Plant Manager in writing, approval or disapproval of items considered under 6.5.1.6(a) through (e) and (j) and (k) l, above.
I b.
Render deteminations in writing with regard to whether or not each item considered under 6.5.1.6(a), (c) and (d) above constitutes an unreviewed safety question.
c.
Make recommendations to the Plant Manager in writing that actions reviewed under 6.5.1.6(b) above did not constitute an unreviewed safety question.
RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the Senior Vice President and Chaiman of the Nuclear l
Operations Review Board.
6.5.2 NUCLEAlr0pERATIONS REVIEW BOARD (NORB)
FUNCTION 6.5.2.1 The NORB shall function to provide independ'ent review and audit of designated activities in the areas of:
a.
Nuclear power plant operatfor.s b.
Nuclear engineering c.
Chemistry and radiochemistry d.
Metallurgy e.
Instrunentation and control f.
Radiological safety g.
Mechanical and electrical engineering h.
Quality assurance practices 7
C0tPOSITION 6.5.2.2 The NORB shall be composed of at l' east four persons including:
l Chaiman:
Senior Vice President Vice Chaiman:
Manager-Nuclear Operations and Administration l
Secretary:
Manager-Safety Audit and Engineering Review i
- Member:.
Manager-Nuclear Engineering and Technical Support k
and other appointed personnel having an academic degree in an engineering or physical science field and a minimum of five years technical experience, of i
which a minimum of three years shall be in one or more of the areas given in 6.5.2.1.
FARLEY-UNIT 1 6-9 AMEN 0 MENT NO. 53
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Senior Reactor Operator.'s License. For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedure shall approve the change.
b.
Proposed changes or modifications to plant nuclear safety-related 7.
structures, systems and components shall be reviewed as designated
'j by the Plant Manager. Each such modification shall be reviewed by i
an individual / group other than the individual / group which designed the modification, but who may be fro,n the same organization as The individual / group which designed the modifications. Propo:ed modifications to plant nuclear safety-related structures, systems d;
and components shall be approved prior to implementation by the Plant Manager.
c.
Proposed tests and experiments which affect plant nuclear safety
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and are not addressed in the Final Safety Analysis Report shall be prepared, reviewed, and approved. Each such test or experiment shall be reviewed by an individual / group other than the individual /
it group which 9tepared the proposed test or experiment. Proposed test and experiments shall be approved before implementation by the t~
i' Plant Manager.
becuIrences reportable pursuant to the Technical Specification 6.0 d.
f and violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which t
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provides recomendations to prevent recurrence. Such reports shall be approved by the Plant Manager and forwarded to the Senior Vice President and to the Chaiman of the Nuclear Operations Review Board.
e.
Individuals responsible for reviews perfonned in accordance with 6.5.3.1.a, 6.5.3.1.b, 6.5.3.1.c, and 6.5.3.1.d shall be members of the plant supervisory staff previously designated by the Plant Manager. Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be performed by the review personnel of the appropriate discipline.
f.
Each review will include a detennination of whether or not an unreviewed safety question is involved.. Pursuant to 10CFR50.59 NRC approval of items involving unreviewed safety question will be obtained prior to Plant Manager approval for implementation.
RECORDS i
6.5'.3'.2 Records of the above activities shall be provided to the Plant t
Manager, PORC and/or NORB as necessary for' required reviews.
FARLEY-UNIT 1 6'-13 AMEN 0 MENT NO. 53 i
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6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
a.
The Commissicn shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
b.
Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the
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Commission shall be reviewed by the PORC and submitted to the NORB and the Senior Vice President.
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6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is viol ated:
a.
The facility 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 Senior Vice President,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 actica taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, and the Senior Vice President for NORB review within 14 days of the violation.
6.8 PROCEDURES AND PROGRAMS
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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 2,1978.
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b.
Refueling operations.
.j c.
Surveillance and test activities of safety related ecuipment.
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d.
Security Plan implementation.
l4 e.
Emergency Plan implementation.
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FARLEY-UNIT 1 6-14 AMENDMENT N0. 53.-
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UNITED STATES j
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NUCLEAR REGULATORY COMMISSION a ?.,3 7
j WASHINGTON. D. C. 20555
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l ALABAMA POWER COMPANY
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1 DOCKET NO. 50-364
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JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 l
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pENDMENTTOFACILITYOPERATINGLICENSE
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ij Amendment No'. 44 1
License No. NPF-8 1.
The Nuclear Regulatory Comission (the.Comission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee)datedMay 14, 1984, complies with the standards aiid requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth ir,10 CFR Chapter I; B._ Jhe, facility will operate in conformity with the applicaticn, as amended, the provisions of the Act, and the regulations of the Comission; i
C.
There is reasonable assurar.ce: (1)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in coripliance with the Comission's regulations; D.
The issuance of this license 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 have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-8 is hereby 11 amended to read as follows:
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i (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 44, are hereby incorporated in the license. The licensee i
shall operate the facility in accordance with the
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a t
Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION.
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Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing Attachmen,t;_ _.
Changes to the Technical 4
Specifications
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Date of Issuance: November 13, 1984 1
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ATTACHM'ENT TO LICENSE AMENDMENT NO.44 AMENDMENT NO.44 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Revised Appendix A as follows:
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6-2 6-2 6-6 6-6 6-9 6-9 6-13 6-13 6-14 6-14
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.1' ADMINISTRATIVE CONTROLS n
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 Supervisor or during his absence from the Control Roan a
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~
designated individual shall be responsible for the Control Room Command t
function. A management directive to this effect, signed by the Senior Vice President responsible for Nuclear Generation, hereafter referred to as -
Senior Vice President, shall be reissued on an annual basis.
6.2 ORGANIZATION 0FFSITE 6.2.1 The offsite organization for facility managenent and technical support shall be as shown on Figure 6.2-1.
i.
FACILITY ' STAFF i
6.2.2 The facility organization shall be as shown on Figure 6.2-2 and:
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.-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, at least one licensed Senior Reactor Operator shall be in the Control Room while the unit is in MODE 1, 2, 3 or 4.
A health physics technician # shall be on site when fuel is in c.
the reactor.
d.
ALL CORE ALTERATIONS shall be 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 site Fire Brigade of at least 5 members shall be maintained onsite at all times.# The Fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
!Th'e" health' physics technician and Fire Br.igade 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 accomodate unexpected absence of the health physics technician and/or Fire Brigade members provided inmediate action is taken to restore the health physics technician and/or Fire Brigade to within the minimum l-requirements.
FARLEY-UNIT 2 6-1 AMENDMENT N0 44 l
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Manager Manager Plant Manager Manager Safety Audit and Nuclear Operations farley Nuclear Engineering Engineering Review-and Administration
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u Supervfsor Staff Plant Staff l
Safety Audit and l
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Figure 6.2-1 Offsite Organization for Facility Management and Technical Support.
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ADMINISTRATIVE CONTROLS l
g 6.2.3 SAFETY AUDIT AND ENGINEERING REVIEW GROUP (SAERG)
FUNCTION l
6.2'.3.1 The SAERG shall function to conduct operational evaluations, c
engineering reviews, and audits for the purpose of improving safety.
?!'
C0!90SITION 1
6.2.3.2 The SAERS shall be composed of multi-disciplined dedicated onsite
~
group with a minimum assigned complement of five engineers or appropriate specialists.
RESPONSIBILITIES 6.2.3.3 The SAERG shall be responsible for the following:
a.
Participating in operational evaluations for improvement of safety wherein such evaluations and reconmiendations therefrom are not limited to the fulfillment of existing programs, policies, procedures, or capabilities of existing equipment and
! 3
_i nsta.11 ations.
- b. ' Systematic engineering reviews of plant performance and activities with results reported independently of onsite operational management to offsite upper management.
c.
Comprehensive plant audits in accordance with audit requirements set forth in quality assurance programs,' licensing doctanents, and other policies and procedures.
AUTHORITY t
6.2.3.4 The onsite SAERG shall carry out its function reporting offsite directly to the Manager-Safety Audit and Engineering Review who in turn reports directly to the Senior Vice President.
l 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor primarily in the assessment of accident and transient occurrences.
6.3 FACILITY STAFF OUALIFICATIONS fa 6.3.1-Each member of the facility staff shall meet or exceed tiie minimum qualifications of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for (1) the Health Physics Supervisor who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
4 FARLEY-UNIT 2 6-6 AMENDMENT NO. 44
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AUTHORITY 6.5.1.7 The PORC shall:
- a.
- Recommend to the Plant Manager in writing, approval or disapproval of items considered under 6.5.1.6(a) through (e) and (j) and (k)
- d above.
'(
b.
Render determinations in writing with regard to whether or not tach l.
item considered under 6.5.1.6(a), (c) and (d) above constitutes an unreviewed safety question.
c.
Make recommendations to the Plant Manager in writing that actions l
reviewed under 6.5.1.6(b) above did not constitute an unreviewed l
safety question.
i
' RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting and copies shall be provided to the Senior Vice President and Chairman of the Nuclear l
Operations Review Board.
.n-l 6.5.2 NUCLEAR OPERATIONS REVIEW BOARD (NORB)
FUNCTION 6.5.2.1 The NORB shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations b.
Nuclear engineering c.
Chemistry and radiochemistry l
d.
Metallurgy e.
Instrtmentation and control f.
Radiological safety g.
Mechanical and electrical engineering h.
Quality assurance practices COWOSITION 6.5.2.2 The NORB shall be composed of at least four persons including:
l Chaiman:
Senior Vice President Vice Chaiman:
Manager-Nuclear Operations and Administration l
.. Secretary:
Manager-Safety Audit and Engineering Review Member:
Manager-Nuclear Engineering and Technical Support and other appointed personnel having an academic degree in an engineering or physical science field and a minimum of five years technical experience, of which a minimum of three years shall be in one or more of the areas given in 6.5.2.1.
FARLEY-UNIT 2 6-9 AMENDMENT NO.44 i
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ADMINISTRATIVE CONTROLS
~ Senior Reactor Operator's 'Licenso. For changes to procedures which may involve a change in intent of. the approved procedures, the person authorized above to approve the procedure shall approve'the change.
b.
Proposed changes or modifications to plant nuclear safety-related
,1,
structures, systems and components shall be reviewed as designated
,. )
by the Plant Manager. Each such modification shall be reviewed by e
an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modifications. Proposed modifications to plant nuclear safety-related structJres, systems and components shall be approved prior to implementation by the Plant Manager.
9 c.
Proposed tests and experiments which affect plant nuclear safety and are not addressed in the Final Safety Analysis Report shall be prepared, reviewed, and approved. Each such test or experiment shall be reviewed by an individual / group other than the individual /
' group which prepared the proposed test or experiment. Proposed test and experiments shall be approved before implementation by the Plant Manager.
d.
Occurrences reportable pursuarit to the Technical Specification 6.0 and violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence. Such reports shall be approved by the Plant Manager and forwarded to the Senior Vice President and to the Chairman of the Nuclear Operations Review Board.
e.
Individuals responsible for reviews performed in accordance with 6.5.3.1.a, 6.5.3.1.b, 6.5.3.1.c, and 6.5.3.1.d shall be members of the plant supervisory staff previously designated by the Plant Manager. Each such review shall include a determination of' whether or not additional, cross-disciplinary, review is necessary. If deemed necessary, such review shall be perfomed by the review personnel of the appropriate discipline.
f.
Each review will include a determination of whether or not an unreviewed safety question is involved. Pursuant to 10CFR50.59 NRC approval of items involving unreviewed safety question will be obtained prior to Plant Manager approval for implementation.
RECORDS
~
6.5.3.2 Records of the above activities shall be provided to the Plant Manager, PORC and/or NORB as necessary for required reviews.
FARLEY-UNIT 2 6-13 AMENDMENT NO. 44 l'
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ADMINISTRATIVE CONTROLS i
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:
i e
a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
s b.
Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the 1(
Commission shall be reviewed by the PORC and submitted to the NORB and the Senior 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 facility shall be placed in at least HDT 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 Senior Vice President,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 circunstances 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, and ti.e Senior Vice President for NORB review within 14 days of the violation.
6.8 PROCEDURES AND 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 2,1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
{
- " d.
Security Plan implementation.
e.
Emergency Plan implementation.
FARLEY-UNIT 2 6-14 AMENDMENT N0.44
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