ML20248B913
| ML20248B913 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/02/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20248B917 | List: |
| References | |
| DPR-51-A-123, NPF-06-A-097 NUDOCS 8906090208 | |
| Download: ML20248B913 (11) | |
Text
_
UNITED STATES L[
.g, NUCLEAR REGULATORY COMMISSION 7.
'j WASHINGTON, D. C. 20555 k...s,/
ARKANSAS POWER AND LIGHT COMPANY DOCKET N0.-50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.123 License No. DPR-51 1.
The Nuclear Regulatory Comission ('the Comission) ' as found that:
h A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated December 12, 1986 and supplemented on April 14, 1988, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic
, and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(i)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, end (ii) that such activities will be cenducted in compliance 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 pub 1M; and E.
The issuance of this emendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
$060lDOCKosooo333 O20e 990602 p
PDC l
)
L+
l l
l 2.
Accordingly, the license is amended by changes to the Technical _
l Specifications as indicated in the attachmer,t to this license
{
amendment, and Paragraph 2.C.(2) of Facility Operating License No.
i DPR-51 is hereby amended to read as follows:
1 2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.123, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of fissuance.
FOR THE NUCLEAR REGULATORY COMMISSION hXL.]A ldJ4-Frederick J. He ' don, Director-
~
.roject Directorate - IV
)
Division of Re, actor Projects _ - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 2, 1989 t'
i
e ATTACHMENT TO LICENSE AMENDMENT NO.123_
l FACILITY OPERATING LICENSE NO. DPR-51 l
DOCKET NO. 50-313 Revise the following page of the Appendix *A" Technical Specifications with the attached page. The revised page is identified by Amendment number and contains a vertical lines indicating the area of change.
REMOVE PAGE INSERT PAGE 123 123 4
i l
l
d.
metallurgy e.
instrumentation and control f.
radiological safety
~
g.
mechanical and electrical engineering h.
quality assurance practices COMPOSITION 6.5.2.2 The Safety Review Committee shall be composed of a Chairman and
~
eight to twelve members which collectively have the experience and competence required by ANSI /ANS-3.1-1981 to review problems in the areas specified in Section 6.5.2.1, a-h.
The"Vice President of Nuclear Operations shall designate, in
~
writing, the Chairman and all SRC members.
The lhairman shall designate, in writing, the alternate Chairman in the absence of the SRC Chairman t
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time. -
CONSULTANTS 6.5.2.4 Consultants shell be utilized as determined by the SRC Chairman to provide ex' pert advice to the SRC.
MEETING FREQUENCY
~
6.5.2.5 The SRC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.
QUORUM 6.5.2.6 The minimum quorum of the SRC necessary for the performance of the SRC' review and audit functions of these technical-specifications shall corisist of the Chairman or his designated a? ternate and at least a majority of the SRC members including altes. nates.
No more than a minority of the quorum shall have line resr.:rnsittility for operaticn of the unit.
1 Amendment No. If, JK, 37, 47, 58, 82, 123 ff,123
. - (MECuf'o
_ UNITED STATES -
'~
g g
NUCLEAR REGULATORY COMMISSION l
5
- j WASHINGTON, D C.20$$5 -
L\\,...../
i ARKANSAS POWER AND LIGHT COMPANY
' DOCKET NO. 50-368 l
l ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No. 97 License No. NPF-6
~ 1.
The Nuclear' Regulatory Comission (the Comission). has found that:
A..
The application for amendment by Arkansas. Power and Light Company
'I (thelicensee)datedDecember 12, 1986.and as' supplemented on April 14, 1988, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic
, and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will cperate in conformity with' the application, as
-amended, the provisions of the Act, and the rules and regulations-of the Comission; 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comen 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.
H 1
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-6 is hereby amended to read a. follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 97, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b2wA.
1 /dS/2,t Frederick J. He don, Director Project Directorate -.IV Division of Reactor Projects - III, IV, Y and Sp'ecial Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 2, 1989 l
_______ - _ - ____ a
4 ATTACHMENT TO LICENSE AMENDMENT NO. 97 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368
- Revise the following pages of the Appendfx A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to meintain document ~
completeness.
REMOVE PAGES.
INSERT PAGES 6-8 6-8 6-9 6-9 4
e
ADMINISTRATIVE CONTROLS f.
Review of events requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written no'.ification to the Commission.
g.
Review of facility operations to detect potential nuclear safety hazards.
h.
Performance of special reviews, investigations or analyses, and reports thereon as requested by the Executive Director, AND Site Operations or the Safety Review Committee.
i.
Review of the Plant Security Plan and implementing procedures and submittal of recommended changes to the Executive Director, AND Site Operations and the Safety Review Committee.
j.
Review of the Emergency Plan and implementing procedures and.
submittal'of recommended changes to the Executive Director, AND Site Operations and Safety Review Committee.
k.
Review of changes to the'0ffsite Dose Calculation Manual and Process Control Program.
AUTHORITY 6.5.1.7 The Plant Safety Committee shall:
+
a.
Recommend in writing their approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (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 Vice President, Nuclear Operations and the Safety Review Committee of disagreement between the PSC and the Executive Director, AND Site Operations; however, the Executive Director, AND Site Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
I RECORDS
- 6. 5.1. 8 The Plant Safety Committee shall maintain written minutes of each PSC meeting that, at a minimum, document the results of all PSC activities l
performed under the responsibility and authority provisions of these i
technical specifications.
Copies shall be provided to the Executive I
Director, AND Site Operations and Chairman of the Safety Review Committee.
i ARKANSAS-UNIT 2 6-7 Amendment No. 5, 17, 25, 52, 68, 7;, 85
7:
r.-- c.
3 I
1
\\
i ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW COMMITTEE (SRC)
FUNCTION j
i 6.5.2.1 The Safety Review Committee shall function to provide independent j
review and audit of designated activities in the areas of:
l a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radiochemistry d.
metallurgy e.
instrumentation and control a
f.
radiological.afety g.
mechanical and electrical engineering h.
quality assurance practices COMPOSITION 6.5.2.2 The Safety Review Committee shall be composed of a Chairman and i
eight to twelve members which collectively have the experience and competence required by ANSI /ANS-3.1-1981 to review problems in the areas specified in Section 6.5.2.1, a-h.
The Vice President, Nuclear Operations shall designate, in writing, the
~
. Chairman and all SRC members.
The Chairman shall designate, in writing, the alternate Chairman in the absence of the SRC Chairman.
l l
I l
ARKANSAS-UNIT 2 6-8 Amendment No. 5, 17, 25, 52, 73, 97
[_
- _ -.--__ -- _ - _- _ ------ - ---- _ - --- -- - o
ADMINISTRATIVE CONTROLS ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
MEETING FREQUENCY 6.5.2.5 The SRC 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.
QUORUM 6.5.2.6 The minimum quorum of the' SRC necessary for the performance of the SRC review and audit functions of these technical specifications shall consist of the Chairman or his desi nated alternate and at least a majority C
of the SRC members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
i i
l i
ARKANSAS-UNIT 2 6-9 Amendment No. 97
ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The SRC shall review:
The safety evaluations for 1) changes to procedures, equipment a.
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.
4 b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59,10 CFR.
Proposed tests or' experiments which involve an unreviewed
}
c.
safety question as defined in Section 50.59,10 CFR.
d.
Proposed changes to Technical Specifications or this Operating License.
Violations of codes, regulations, orders Technical ' Specifications, e.
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.
9 Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
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.
e 1.
Reports and meetings minutes of the Plant Safety Committee.
~
j.
Proposed changes to the ODCM and PCP.
ARKANSAS - UNIT 2 6-10 Amendment No. 60
_ - _. _ - - - - - - - - _ _ - - _ _ _ _ - - _ - - -