ML20116K165
| ML20116K165 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/10/1992 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20116K143 | List: |
| References | |
| NUDOCS 9211170050 | |
| Download: ML20116K165 (18) | |
Text
.
1.
PROPOSED ANO-1 TECilNICAI. SPECIFICATIONS CilANGJES P
7211170050 921110 PDR
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6,2.2.1 Administratis. controls shall be established to-limit the amount of overtime worked by plant _ staff performing safety-related functions. These administrative controls shall be in accordance with the guidance provided_by the NRC Policy Statement on working hours (Generic Letter 82-12).
6.3.
FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the racility staff chall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable position, except for (1) the designated radiation protection manager, who shall meet or exceed the qualifications of
'l Regulatory Guide 1.8, September 1975_and (2) the Shift Technical Advisor who shall havu a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 IEAINING 6.4.1 A retraining and replacement training program for the. uni' staff shall be maintained under the direction of the Manager,-
Training and Emergency Planning and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CPR Part 55, 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager, Training and _ Emergency Planning and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 except for Fire Brigade training sessions which shall.be held at least_ quarterly.
6.5 IMJEW AND AUDlI 6.5.1 Plant Safety Committee-(PSC) Function-6.5.1.1 The Plant 1 Safety-Committee shall function to advise the General Manager, Plant Operations and Plant Manager, A10-1 on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Safety Committee shall be composed of-eight members-
- of ANO onsite management organization who have the _ technical experience and competence-required by ANSI /ANS_3.1-1981 for Managers, Professional-Technical, or Engineering _and Techni-91' Support Personnel. -The PSC Chairman shall ensure that adequate
-expertise.is present during meetin,gs to-evalua.e material before the PSC.
In addition, thw General Maner,er, Plant Operations shall designate in writing a PSCf5'4 airman and at least one Alternate Chairman.
Amendment No, if,79,3f,$1, 117a
'ff,59,59,ff,fisf$,99,199,ill>12f,1fb>lfl
1 ALTERNATES l
1 6.5.1.3 All alternate members shall be oppointed in writing by the PSC Chairman to serve on a temporary basis; however, no more than two alternatos shall participate as vnting members t, PSC act "*1 tics at any one time.
HEETING FREOUENCY 6.5.1.4 The PSC shall meet at least on() por calendar month and as convened by the PSC Chairman or his designated alternato.
l l
OUORUM 6.5.1.5 The minimum quorum of the PSC necessary for the performance of-the PSC responsibility and authority provisions of theso technical specifications shall consist of the Chairman or his designated alternato and four members including alternates.
RESPONSIBILITIES o.5.1.6 The Plant Safety Committee shall be responsible for:
a.
Review of 1) all station administrativo procedures i
recommended in Appendix A of Reg Guido 1.33, November, 1972, and changes in intent thoroto, 2) changes to the ANO-1 Emergency Operating Procedures required-to implement the requirements of NUREG-0737 and Supplement I to NUREG-0737 as stated in-Section:7.1 of _ Generic Lotter 82-33, and 3)'any other proposed procedures or j
rovisions thoroto an determined by the General Manager, Plant 0~~tations or Plant Manager, ANO-1.
b.
Review of all-proposed tests and experiments that affect nuclear safety.
c.
Review 4( all proposed changes to the Appendix "A" Technical Specifications.-
d.
Review of all proposed changes or modifications to plant systems or equipment _that affect nuclear safety.
o.
Investigation of all violations of tho-Technical.
Specifications, including the preparation and forwarding of _ reports covering evaluation and recommendations to provent recurrence to the Plant Manager, ANO-lo.Getieral_ Manager, Plant. Operations and to'the Chairman of the Safoty Review Committen.
f.
' Review of REPORTABLE EVENTS.
Review of facility _ operations to detect potential
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nuclear safety har,ards.
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Performanco of special reviews,-investigations, or analyscs and reports then cen as requested by the Plant Manager, ANO-1, l.
General Manager, Plant Operations or the Safety Review Committee.
1.
Review of the Plant Security Plan and submittal of l
recommended changes to the General Manager, Plant i
Operations and the Safety Review Committen.
j.
Review of the Emergency Plan and submittal of recommendnd l
?
changes to the General Hahager, Plant Operations and the i
Safety Review Committee.
k.
Review of changes to the Offsite Doso Calculation Manual and the Process Control Program.
1.
Review of changes to the Fire Protection Program and' submittal of recommended changes to the Gonoral Managor, Plant Operations and Safety Review Committee, m.
Review of proposed procedures and changes to procedures which involve an unreviewed safety question as defined in 10CFR50.59.
AUTHORITY 6.5.1.7.
The Plant Safety Committee shallt a.
Recommend in writing their approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
y b.
Render datorminations in writing with regard to whether or not I
cach item considered under 6.5.1.6(a) through (e) above constitutes an unroviewed safety question.
1-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, Operations ANO and the Safety Review Committee of disagreement betwoon the PSC and the Plant Manager, ANO-1 or the General Manager, Plant Operations; hownvor, the General Manager, Plant Operations shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
RECORDS l
6.5.1.8 The Plant Safety Committen shall maintain written minutos of each-PSC :: cal.ina that, at a minimum, document the results of all PSC activities performed under the responsibility and authority provisions of theco technical specifications.. Copies shall be provided to the Plant Manager, ANO-1, General Manager, Plant Operations and Chairman of the Safety Review Committen.
6.5.2 Safety Review Committee (SRC)
.3 S
Amendment No. Jf>,$A,)/,47,58,$F, 122 ff,H :199,11F,161,191 155 a
PUNCT10N 6.5.2.1 The Safety Review Committee shall function to provide independent review and audit of designated activities in the arcas of:
a.
nucicar power plant operations b.
nucient engineering chemistry nnd rndiochemistry c.
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i Amendment No.
122n
l TJicpNICA1._REyll.t p" CONTR0b PROCI'SS required by Specification 6.8.1 and other procedures 6.5.3 Proc.
u which unect nuclear safety, as determined by the General Manager, plant Operations, and changes thereto, shall be reviewed as follows:
a.
Each procedure or change shall be independently reviewed by a qualified individual knowledgeable in the area affected; other than the individual who prepared the procedure or procedure change. This review shall include a determination of whether or not additional cross-disciplinary reviews are necessary.
If deemet necessary, the reviews s'ill be performed by the re/ low personnel of the appropriate discipline (s),
b.
Individuals perfot.-Ini, these reviews shall meet the applienble qualifications of ANSI /ANS 3.1-1981, Section 4.0, excluding subsections 4.3.2 and 4.5, and be approved to perform these reviews in a given aren by the General Hanngrr, Plant Operations.
Those procedures and programs specified by 6.5.1.6, and c.
changes in intent thereto, shall be reviewed by the PSC and approved by t he General Manager, Plant Operations, or ANO-1 plant Manager prior to implementation.
d.
Those procedures and programs specified by r
'.1.
and changes in intent thereto, with the excq.fon of those specified i n 6. 5.1,6, shall be approved by the appropriate Department Head as specified in station administrative procedures.
Review of the procedure or procedure change will include a e.
determination of whether or not an unreviewed safety question is involved.
This determination will be based on the review of a written safety evaluation prepared by a qualified individual, or documentation that a
safety evaluation is not required.
pSC review, SRC review, and NRC approval of items involving unrevirved safety questions shall be obtained prior to station approval for implementation.
f.
Written records of reviews performed in accordance with this specification shall be prepared and maintained in accordance with Specification 6.9.
Amendment No.
125a
+
6.8.2 Each procedure of 6.8.1 above, and changes in intent thoroto, shall be reviewed and approved as required by 6.5 prior t.o implementation and reviewed periodically as not forth in administrativo procedures.
6.8.3
-Changes to procedures of 6.8.1 above may be made and implemented prior to obtaining the review and approval required in 6.8.2 above providod:
a.
The intent of the original procedure is not altered, b.
The chango is approved by two members of the plant management staf f, at least one of whom holds a Senior Ronctor Operator's 11conso on Unit 1.
c.
The chango is document ed, reviewed and approved as required by 6.5, within 14 days of impicmentation.
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i ADH1IlllIEA11YE CiWIEDLS 6.3 UNIT STAFF _00AldFICATIONS 6.3.1 Each member of the unit. staff shall moot or w ood the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the designated radiation protection manager, who shall meet or exceed the i
qualifications of Regulatory Guido 1.8, September 1975, and (2) the Shif t -
Technical Advisor who shall have a bachelors degrco or equivalent in a scinntific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
.6.4_'GAINIRQ 6.4.1 A retraining and replacement training program for tho unit staff shall be maintained under the direction of the Manager, Training and Emorgoney Planning and shall moot or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of' 10 CFR Part 55.
6.4.2 DELETED 6.5 REVIEW AND AUDIT M.1 PLANT SAFETY _ COMMITTEE (PSC)
FUNCTIDN 6.5.1.1 The Plant Safety Committee shall function to_ advise the General Manager, Plant Operations and Plant Manager, ANO-2 on all matters related to nuclerir safety.
C0H1'OSIT10N 6.5.1.2 The Plant Safety Committen shall be composed of eight members of ANO onsito management organization (except as discussed under 6.5.1.3) who have the technical experianco and competence required by ANSI /ANS 3.1-1981 for Managers, Professional-Technical, or Engincoring and Technical Support personnel.
The PSC Chairman shall ensure that' adequate expertise is present during meetings to evaluate material before the PSC.
In addition, the General Manager, Plant Operations-shall. designato. in writing a PSC Chairman and at 1 cast one Alternato Chairman.
6.5.1.3 If Core Protection Calculator (CPC) Software is being reviewod a-4 nuclear sof tware expert shall be present as a voting-member.
If one of the members of the Plant Safety Committee meets-the qualification requirements for this position, the requirement to have this member is satisfied. This-membership may_be filled by two appropriately qualified individuals who shall ballot with a single combined voto. Generic quellfications for this
- membcrship shall be as follows:
l ARKANSAS - UNIT 2 6-5 Amendment No. ),J/,ff..
10,19,11,/1,15, 95,l H,119 111
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AD31NISIRAIlXLGONIROLS i
l Dne. Individual i
The Nucicar Software Export shall have as a minimum a Bachelor's degree in Science or Engineering, Nucicar preferred (in accordance with ANSI N16.1).-
In addition, ho shall have a minimum of four ynars of technical exporlence, of which a minimum of two years shall be in Nuclear Engineering _and a minimum shall bo in Softwaro Enginocring.
(Software Enginocring la that l
hranch of science and technology which deals with the design and use of
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software.
Sof tware Engineering is a disciplino directed to the production and modification of computer programs that are correct, officient.-
flexibic, maintainable, and unders, dabic, in reasonable timo spans. and.
at reasonabin costs.) The two yonrs of technical experienco in Sof twaro Enginocring may be general sof twarn experlenen not. norussarily related to
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the software of the Coro Protection Calculator System, One of these two years-of exper.icnco shall be with certiflod computer programs, j
i Two. Irdividuals One of the individuals shall moot the requirements of the Nuclear Engineering portion of the above. The second individual shall have a Bachelor of Science degree (digital computer speciality) and meet the Software Engineering requirements of the above, r
The membership (t.hn Nuclear. Sof tware Expert or the Digital Computer Specialist) shall be knowledgeable of the Core Protection Calculator System with regard to:
T'n software modules, their interactions with each other and with n
a.
thn data base.
r b.
The relationship between operator's modulo inputs and the trip variables.
c.
The relationship betwcon sensor input signala-and the-trip variable.
j d.
The design basis of the Core Protection Calculator System.
o.
Thn approved. software change proceduro and documentat. ion-
..y-requirements of a sof tware chango.
f.
1hn security of the computer memory and access'procsduros to'the memory.
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' ARKANSAS UNIT 2' 6-Sa-Amendment No.'J/,114.
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AD.tmdEIRAILYE_C2NIMM ALTERNATES 6.5.1.4 All alternate members shall be appointed in writing by the PSC Chairman to norve on a temporary basis; however, no more than two alternates shall participato as voting memborn in PSC activities at any_ one timo.
tiLETJHG._IREWLHCl 6.5.1.5 The PSC shall moot at least once por calendar month and as convened by the PSC Chairman or his designated alternate.
OUORUM 6.5.1.6 The minimum quorum of the PSC necessary for the performance of the PSC responsibility and authority provisions of those technical specifications shall consist of the Chairman or his designated alternato and four members including alternatos.
RESPONSIBlLLIIES 6.5.1.7 The Plant Safet y Committoo shall be responsiblo for a.
Review of 1) all station administrativo proceduros recommended in Appendix A of Reg Guido 1.33, Revision 2, lechruary, 1978, and changes in intent thornto, 2) changes to the ANO-2 Emergency Operating Proceduros required to implement. the requirements of NUREG-0737 and Supplemont I to NUREG-0737 as stated in Section 7.1 of Generic 1. otter 82-33, 3) changes to Coro Protection Calculator.(CPC)
Software, and 4) any other proposed proceduros or changos t heret o as dotormined by the Coneral Manager, Plant Operatioes or Plant Manager, ANO-2.
b.
Review of all proposed tests and experiments that affect nuclear safety, Roview of ali proposed changes to Appendix "A" Technical c.
Specificationsi d.
Review of all proposed changos or modifications to unit systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical c.
Specifications, including tho preparation and forwarding of reports covering evaluation and recommendation to provent recurrence to the Plant Manager, ANO-2, General Manager, t
Plant Operations and to the Chairman of the Safoty Review l
Committoo.
ARKANSAS _- UNIT 2 6-6 Amendment No. f,17,55,/5,55 75, lH,117
.=
AQ!ijNISTRATIVE CONIRQLS f.
Review of all REPORTAB!I EVENTS.
t g.
Review of facility operations to detect potential nuclear safety
- hazards, b.
Performance of special revicts, investigations or analyses, and i
reports thereon as r9 quested by the Plant Manager, ANO-2, Genorni Hanager, Plant Operations or the Safety Review Committee.
i.
Review of the Plant. Security Plan and submit'tal of recommended I
changes to the General Hanager, Plant Operations and the Safety.
Review Committee.
j.
Review of the Emergency Plan and submittal of recommended changes l
to the General Manager, Plant Operations and Safety Review Committ.o.
i k.
Review of changen to the Offsite Doso Calculation Manual and Process Control Program.
1.
Review of changes to the Fire Protection Program and submittal of recommended changes to the General Manager, Plant Operations and Safety Review Committee, i
m.
Review of proposed procedures and changes to procedures which involvn an unrnviewed safety question as defined in 10CFR50.59.
l AVIll0R1TY 6.5.1.8 The Plant Safoty Committee shall:
n.
Recommend in writing their approval or dianpproval of items considered under 6.5.1.6(a) through (d) above.
b.
Rondor determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (c) above-constitutes an unreviewed safety, question.
Ia c.
Provido written 1.otification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vico President, Operations ANO and the Fafety Review' Committee of ohj diangreement between the PSC and.the Plant Manager, ANO-2 or' the General Manager, Plant _ Operations; however, the General.
j Hanager, Plant Operations shall have responsibility for resolution of such-disagreements pursuant to.6.1.1 abcve, t
i.~
RECORDS 6.-5.1.9 The Plant Safety Committen shall maintain written minutes.of each PSC ricotirw ta iti at'a minimum, document. the results of all PSC activities perfors.ed under the responsibility and authority provisions of' theso i
i i
technical specifications. Copies shall be provided to the Plant-Manager, 4
q ANO-2, General Manager, Plant Operations and Chairman of tho Safety Review Committee.
"e ARKANSAS J UNIT 2 6 Amendment No. 5,J1,25,52 f9,
??,15,91. 95,11F,119,131
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fui2_SAll11_EY.11X30!id11 TEE f SRCl 11 MCI 1DN 6.5.2.1 The Safety Review Commit Lee shall function to provide independent review and audit of designat ed act ivities in the areas of:
n.
nuclent power pinnt operatiotis b.
nuclent engineering chemistry and rndlochemistry c.
d.
metallurgy
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c.
Instrumr.. ation and control f.
radiological safety g.
mechanical and electrical engineering h.
quality nssurance practices CD!11'QSlI103 6.5.2.2 The Safety Review Committen shall bn composed of a Chairman and eight to twelve members which collectively have the experienco and competence required by ANSI /ANS-3.1-1981 to review problems in the arens specified in Section 6.5.2.1, a-h.
The Vice Pres ident, Operations ANO shall designat e, in writing, the Chairman and all SRC members.
The Chairman shall designate, in writing, the alt.ornat o Chairman in the absence of the Si?C Chairman.
ARKANSAS - UNIT 2 6-8 Amendment No. 5,J/,25,J/,73 77,78,114
AMihaEIRAIHILCMIROLS AUDITS 6.5.2.8 Audits of unit activitien shell be performed under the cognizance of the SRC.
These audits shall encompass:
a.
The conformance of uni.t operation to provisions coatained within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performanco, training, and qualifications of the entire unit staf f at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in unit equipment, structure, systems, or method of operation that af fect nuclear safety at least once per 6 months.
d.
The performanco of activities required by the Operational Quality Assurance Program to meet the criteria of 10 CFR 50, Appendix "B", at least once per 24 months.
The racility Emergency Plan and implementing procedures at least c.
once per 12 months.
f.
The Facility. Security Plan and implementing procedures at least once per 12 months.
g.
Awy other area of unit operation considered. appropriate by the SRC or the Vice president.. Operations ANO.
h.
The Facility Fire Protection Program and impicmenting procedures at least once per 24 months.
i 1.
An independent fire protection and loss prevention program l-inspection and audit shall be performed ~at least once por 12 months utilizing either qualified of fsite licensee personnel. or an outside fire protection-firm.
j.
The Offsite Dose Calculation Manual and Process Control Program and implementing procedures at least once per 24 months.
r k.
An inspection and audit of the fire protection and loss prevention program shall be performed by a quellflod outside: fire-l consultant at least once per 36 months.
AUTHORITY 6.5.2.9 The SRC shall report to and advise the Vice President, Operations ANO on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
ARKANSAS - UNIT 2-6-11 Amendment-No. JJ,1),AJ,52, ff.11,31,114' n
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ADMEISJRAT1YEJgNIRQ1S I
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6.5.2.10 Records of SRC activities shall be prepared, approved and distributed as Indicated below:
a.
Minutes of each SRC meeting shall be prepared, approved and forwarded to the Vico president, Operations ANO within 14 days following each meeting.
l b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vico president, Operations ANO within 14 days following completion of the review, c.
Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice president, Operations ANO and to the management positions responsible for the areas audited within 30 days af ter complet ion of the audit.
TECllNICAL REVIEW AND CONTR0b PROCESS 6.5.3 procedures required by Specification 6.8.1 and other procedures which affect nuclear safety, as determined by the General Manager, Plant Operations, and changes thereto, shall be reviewed as follows:
a.
Each proceduro or change shall_be independently reviewed by a qualified individual knowledgeable in the area affected other than the individual who prepared the procedure or proceduro change. This review shall includo a determination of whether or not additional cross-discil linary reviews are necessary.
If deemed necessary, the reviews shall bo performed by the review personnel of the appropriate disciplino(s).
b.
Individuals performing those reviews shall moet the applicable qualifications of ANS1/ANS 3.1-1981, Section 4.0,,
excluding subsections 4.3.2 and.4.5, and be approved to e
perform theso reviews in a given area by the General.
Manager, plant Operations, Those procedures and_ programs specified by.6.5.1.7, and c.
changes in intent thereto, shall be reviewed by the pSC-and approved by the General Manager, plant Operations, or ANO-2 piant Manager prior to implementation.
d.
Those procedures and programs specified by 6.8.1,1and changes in intent thoroto, with the exception of those specified in 6.5.1.7, shall be approved by 1the appropriate Department Head as specified in station administrative procedures.
L ARKANSAS - UNIT 2 6-12 Amendment No. JJ,J/,25,52
/
15,91, 95,JJF I
i e.
Review of the proceduro or proceduro change will' include a determination of whether or not an unroviewed safety question is involved.
This determination will be based on the review of a written safety ovaluation prepared by a qualified individual, or documentation that a safety evaluation is not required.
PSC review, SRC review, and NRC approval of items involving unroviewed safety questions 4
shall be obtained prior to station approval for implementation.
f.
Written records of reviews performed in accordance with this specification shall be prepared and maintained in accordanco with Specification 6.10.
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall bo.taken for REPORTABLE EVENTS:
a.
A report shall be submitted to the Commiss.fon pursuant to the requirements of Section 50.73 to 10CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PSC and, the results of this review shall be submitted to the SRC and the Vice President, Operations ANO.
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6-12a p
s ADM!US.IFAIJXE.WHIMLs 6.7 SAPETY LIMIT V10LATI_0N 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 il0T STANDBY within ono hour.
b.
The Vico President, Operations ANO and the SRC shall be notiflod within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
The Nuclear Regulatory Commission shall be notified pursuant to 10CFR50.72 and a report submitted pursuant to the requiromonts of 10CFR50.36 and Specification 6.6.
h.8 PROC 1;DUJES 6.8.1 Written proceduros shall bn establis'ad, implemented and maintained covering the nctivltion referenced below:
The applicable procedures recommended in Appendix "A" of a.
Regulatory Guido 1.33. Revision 2, February 1978.
b.
Refueling o^ orations, c.
Surve il lant.t and tont activition of safety related equipment.
d.
Er urity Plan implementation, n.
Emergency Plan implomentation, f.
Firo Protection Program implomentation.
g.
Modification el Core Protection Calculator (CPC) Addressablo Constants.
Those proceduros should includo provisions to assure that sufficient margin is maintained in CPC Type 1 addressable constants to avoid excesslyn operator intoraction with the CPCs during reactar operation.
i NOTE:
Modifications to the CPC software (including changes of algorithms and fuel cycle specific data) shall be erformed in accordance with the most recent version of p'CPC Protection Algorithm Sof tware Change Proceduro,"
CEN-39(A)-P that has been datormined to be applicable to
![
the facility.
Additions or deletions to CPC addressable constants or changes to addressable constant software limit values shall not be implemented without prior NRC approval.
p-h.
Now and spent fuel storage, i.
J.
Postaccident sampling (includes sampling of reactor coolant, i'
radioactive fodinos and particulatos in plant gaseous offluent, and the containment.atmosphoro).
6.8.2 Each procedure of 6.8.1 above, the changes in intent thereto, shall-be reviewed and approved as required by 6.5 prior to implementation and
.l.
reviewed periodically as set forth in administrativo proceduros.
4 ARKANSAS - UNIT 2 6-13 Amendment No. 14,26,4),51, f t, f?,11,11, f 5,91, 96,114,119 -
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4 ADM NIS R ATIVE COS 3 QL 6.8.3 Changes to procedures of 6.8.1 above may be modo and implemented prior to obtaining the review and approval required in o.8.2 above provided:
a.
The intent of the original proceduto is not altered, b.
The chango is approved by two members of the plant management staf f, at ionst one of whom holds a Senior Reactor Operator's hicense on Unit 2.
c.
The change is documented, reviewed and approved as required by 6.5, vithin 14 days of implementation.
6.9 RElvgIgg_3EQUIEEEHIs RDUTINE REPDRIS 6.9.1 In addition to thn applicable reporting rnquirements of Title 10, Codo of Federal Regulations, the following reports shall be submitted to the Administrator of the Regional Offico unless otherwise noted.
STARTUp REPORI 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) roccipt of an operating licenso, (2) amendment to the license involving a planned increase in power levn!, (3) installation of fuel that has a dif ferenc design or has been manuf actured by a dif ferent fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performanco of the plant.
6.9.1.2 The startup repor t shall address each of the tests identified in-the FSAR and shall include a description of the measured values of the operating conditions or charactoristics obtained during the test program and a co*
rinon of these values with design predictions and specifictasons.
Any correctivo actions that woro required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments-shall bo included in this report.
6.9.1.3 Startup reports shall bn submitted within (1) 90 days following completion of the startup test program, (2) 90. days following resumption:
or_ commencement of commercial pownr operation, or (3) 9 months following initial criticality, whichever is earliest.
If t.he Startup; Report does not cover all three events'(1.c., initial criticality, completion of startup_ test program, and resumption or commencement of commercial power operation), supplementary reports shall bo submitted at least every three months _until all three events have been completed.
ARKANSAS - UNIT 2 6-14 Amendment No. ),52,//,55',
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