ML17221A734
| ML17221A734 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/20/1988 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17221A733 | List: |
| References | |
| NUDOCS 8804280360 | |
| Download: ML17221A734 (20) | |
Text
6. O AQMINISTRATIVE CONTROLS RESPONS IBILITY 6.1,1 The Plant Manager shall bc responsible for overall unit operation and sha11 de1egatc in writing the succession to this responsfbflfty d
absence.
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<cc F c..'Je k -N~~/c 6.1.2 Thc Shift Supervisor, or during his absence from thc c ntro room a
designated individual, shall be responsible for the control ro m comnand A
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- 6. 2 ORGANIZATION OFFSITE X~ge.~+ Af&cI Cd UNIT STAFF 6.2.2 The unit organfzatfon shall IDCjCcyk fD 6 CA QllD4Jg~p A
a.
Each on duty shift shall be composed of at least the mfnfmvm shift crew composition shown fn Table 6.2-1.
b.
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d.
At least one licensed Reactor Operator shall be fn the control room when fuel fs fn the reactor.
In addition, while the reactor fs fn HOOE 1, 2, 3, or 4, at least one lfcensed Senior Reactor Operator shall be fn the control rool.
A health physics technfcfan shall be on sfte when fuel fs in the reactor.
All CORE ALTERATIONS shall be observed by a 1 fcensed operator and supervfsed by efther a licensed Senfor Reactor Operator or Senior Reactor Operator Lfefted to Fuel Handlfng who has no other concurrent responsfbflftfes durfng thfs operatfon.
The SRO. fn charge of-fuel handlfng normally supervfses from the control room and has the flexfbflftyto directly supervise at either the refueling deck or the spent, fuel pool.
A Site Ffre Brfgade>of at least ffve,members shall be maintained onsfte at all times The Ffre Brfgade shall not fttclude the shift supervisor.
the STA, nor the two other members of'the 0 The health physics technfcfan and Ffre Srfgade caaposftfon say be less th<<
the mfnfmm requfrements for a perfod of tfse not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> fn order
,to accoaeodate unexpected
- absence, provided faaedfate action fs taken to ffll the requfred posftfons.
'T. LUCIE - UNIT 1 6-1 Amendment No. Zf. 6g 8804280360 880420 PDR ADGCK 05000335 P
Onsite and Offsite Or anization 6.2. I 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, Liges of authority, responsibility and communication shall be estab1ished and defined fr om the highest management levels thr ough intermediate levels to and including all operating organization positions.
Those re-lationships shall be documented and updated, as appropriate, in the form, of organizational charts.
These organizational charts will be documented
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b.
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 s
continue nu ar safety is assured.
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for overall unit safe operation and shall have control over those onsite resources neceasary for safe operation and maintenance of the plant.
d.
Although the individuals who train the operating staff and those who carry out the quality assurance functions say report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.
Although health physics individuals may-report to any appropriate man'ager onsite, for matters relating to radiological health and safety of employees and the public, the health, physics manager shall have direct access to that onsite individual having 'responsibility for overall unit management.
Health physics personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.
ADMINISTRATIVE CONTROLS minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a
fire emergency.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, 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 plant is operating.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance o~
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 per iods, 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 by the Plant Manager or his deputy, or 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 individ-ual 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.
SHIFT TECHNICAL ADVISOR 6.2.3 The Shift Technical Advisor function is to provide on shVt advisory technical support in the areas of thermal hydraulics, reactor engineeri'rrg, and plant analysis with ard td the safe operation of the unit.
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ST.
LUCIE - UNIT 1 6-5 Amendment No. 69
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ADMINISTRATIVE CONT ALTERNATES 6.5.1.3 A11 alternate member s shall be appointed in writing by the FRG Chai-man to serve on a temporary basis;
- however, no more than two alternates shall participate as voting members in FRG activities at any one time:.
MEETING FRE UENCY 6.5.1.4 The FRG shall meet at least once per calendar month and as convened by the FRG Chairman or hfs designated alternate.
QUORUM r
6.5.1.5 The quorum of the FRG necessary for the performance of the FRG respons-ibility and authority provisions of these Technical Specifications shall consist of the Chairman or hfs designated alternate and four aembers including alternates.
RESPONSIBILITIES 6.5.1.6 The Facility Review Group shall be responsfble for:
a.
b.
Review of (1) all procedures required by Specfffcatfon 6.8 and changes
- thereto, (2) all programs required by Specfffcatfon 6.8.
and changes
- thereto, and (3) any other proposed procedures or changes thereto as detersfned by the Plant Manager to affect nuclear safety.
Review of all proposed tests and experfmnts that affect nuclear safety.
c.
Revfew of all proposed changes to Appendfx I Technfcal Specfffcatfons.
d.
h.
Revfew of all proposed changes or modfffcatfons to unft s tems or equipment that affect nuclear safety.
Sunni'ra fres,1mb -hied >a Investfgatfon of all vfolatfons= of the Technfcal Spec) fcatfons, fncludfng the preparation and forwardfng of reports covering evalua--
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, and to the
. Chafrman of the Company Nuclear Revfew Board.
Review of all REPORTABLE EVENTS.
Revfew of unft operatfons to detect po'tentfal nuclear~afety hazards.
r.
Performance of specfal revfews, fnvestfgatfons or analyses and reports thereon as requested by the Plant Manager or. the Company Nuclear Review Board.
.ST, LUCIE - UNIT 1 6-7 Amendment No. $P.
69
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ADMIIIISTRATIVE CONQLS m,
Review of the Security Plan and implementing procedures and submittal of recomended changes to the Company Nuclear Review Board.
Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Company Nuclear Review Board.
Review of every unp1anned on-site rel'ease of radioactive material to the environs including the preparation of reports covering evaluation, recomnendatfons and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the nd o
he Company Nuc1ear Revfew Board.
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Review of changes to the PROCESS CONTROL PROGRAN and the OFFSITE 00SE CALCULATION MANUAL and RADNSTE TREATMENT SYSTEMS.
Review and documentation of-)udgment concernfng prolonged operation fn bypass, channel trip. and/or repair of defective protection channels of process variables placed fn bypass since the 1ast FRG meeting.
AUTHORITY 6.5.1.7 The Facility Review Group shall.
a.
Recoomend fn writing to the Plant-Nanager, approval or disapproval of items considered under Specifications 6.5.1.6.a through d above.
b.
Render determinations fn writing wfth regard to whether or not each item considered under Specfffcatfons 6.5.1.6 a through e above constitutes an unrevfewed safety question.
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c.
Provfde written notfffcatfon within 2l hours to the n
the Company Nuclear Review Board of dfsagreement between the FRG and the Plant Nanager; however, the Plant Nanager shall have responsibility for resolution of such dfsagreements pursuant to Speci ffcatfon 6.1.1 above.
RECOROS 6.5.1.8 The Facility Review Group shall maintain written efnutes of each FRG meeting that, at a mfnfmm, document the results of all FJSactfvftfes performed under the responsibility and authority provisions of these T
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fd d t pd the Chafrman of the Company Nuclear Review Board.
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ST. LUCIE - UNIT'1 6-8 Amendment No. H.72
AOMINISTRAT IVE CONTROLS AUTHORITY 6.5.2.9 The CNRB sha11 report to and advise the Executive Vice.Presfdent on those areas of responsibility specifed in'pecifications 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of CNRB activities shall be prepared, approved and distrib-uted as indicated below:
Minutes of each CNRB meeting shall be prepared, approved and forwarded to the Executive Vice President within 14 days following each meeting.
.b.
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Reports of reviews encompassed by Section 6.5.2.7 above, shell be-
- prepared, approved and forwarded to the Executive.Vice President wfthfn 14 days following completion of the review.
Audit reports encompassed by Specfffcatfon 6.5.2.8 above, shall be forwarded to the Executive Vice President and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.
I 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Ceanfssfon shall be notfffed and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be revfewed by the FRG, and the resu1ts of the review shall be submftted to the CNRB d th 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken fn the event e Safety Limf violated:
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a.
The NRC Operations Center shall be notified by lep ne as soon t
Ihl d I ll hathi t
I Th and the CNRB shall'be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
A Safety Lfmft Vfolatfon Report shall be prepared.
The report shall be reviewed by the FRS.
This report shall descrfbe (1) applicable circumstances preceding the violation, (2) effects of ghe violation upon facflfty components, systems or structures, and (3) corrective action taken to prevent recurrence.
ST.
LUCIE - UNIT 1 6-12 AmenOnent No. 69
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ADMINISTRATI VE CONTROLS c ~
d.
The Safety Limit Violation Report shall be submitted to the Comnfssfon, the CNRB and the within 14 days of the
, vio ation.
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Critical operation o
the unit shall not be resumed until authorized by the Comnission.
6.8 PROCEDURES ANO PROGRAMS 6.8.1 Mrfttcn procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures rccomncndcd fn Appendix "A" of Regulatory Guide 1.33, Revision 2, February
- 1978, and those.required for implementing the requirements of NUREG 0737.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equfpmcnt.
d.
Security Plan implementation.
e.
Emergency Plan fmplcmcntatfon.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAN implementation.
h.
OFFSITE 00SE CALCULATION NINUAL fmplementatfon.
gualfty Control Prograw for effluent Nonftorfng, using the guidance fn Regulatory Guide 1.21. Revision 1, June 1974.
- 3.
equality Control Program for environmental oonftorfng using thc guidance fn Regulatory Guide 4.1, Revfsfon 1, April 1975.
6.8.2 Each procedure of Specification 6.8.1a through f. above, and changes thereto, shall be reviewed by the FRG and shall be approved by the Plant Manager prior to fmplementatfon and shall be reviewed perfodfcally as set forth in admfnfstratf ve procedures.
6.8.3 Temporary changes to procedures of Specfffcatfon 6.8.1a through f.
above may be made provided:.
a.
The intent of the orfgfnal procedure fs not altered.
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b.
The change is approved by two members of the plant wanagement staff, at least one of whaa holds.a Senior Reactor Operator's License on the unit affected.
. ST.
LUCIE - UNIT 1
/i H
6-13 Amendment No. RS.Sf. 69
I
'AOMIHISTRATIVE COHTROLS
- 6. 1 RESPONSIBILITY
- 6. 1. 1 The Plant Manager shall be responsible for overall unit oyeratfon and shall delegate in writing Che succession Co this responsibility durf absence.
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6.1.2 The Shift Superviso~,
or during hfs absence froe the c ntrol room, a
designated individual, shall be responsible for the control ro m coaeand function.
A aanagement directive to this effect signed by the shall be reissued to all stat)on personnel on an annual basis.
- 6. 2 ORGANIZATION OFFSITE
~ cc~V hH ~<<l UNIT STAFF 6.2.2 The unit organization shall 5vhjcc ~ Q Kc. Q//y~,'
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Aaendiient No. l3 a.
Each on duty shift shall be coaposed of at least the afnfaixs shift cree coaposftfon shen fn Table 6.2-1.
b.
At least one licensed Reactor Operator shall be fn the control rooa Men fuel fs in the reactor.
In addition, bafle the reactor fs in MOOE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be fn the control rooe.
c.
A health physics technician shall be on site ~n fuel fs fn the reactor.
d.
All CORE ALTERATIONS shall be observed by a lfcensed operator and supervised by either a licensed Senfor Reactor Operator or Senior Reactor Operator Lfafted to Fuel Handling ~ has no other concurrent responsibilities during this operation.
The SRO fn charge of fuel handling novelly supervises frow the control rooe an4 has Che flexi-bility to directly supervfse at either the refueling deck or the spent'uel pool.
e.
A site Ffre brigade of at least five aeabers shall be aafntafned onsite at all tfaes.
The Fire Brigade shall not include the Shift Supervisor, the STA, nor the tm. other eeabers of the afnfma shift czar necessary for safe shutdevn of the unit and any personnel required for other essential functions during a fire eaergency.
f.
A&fnfstrati ve procedures shall be developed and fepleafhtad to 1 fait the irking hours of unit staff ~ perforce safety related functions; e.g., senior reactor operators, reactor operators, health physfcfsts, auxf1 fary operators, and key aafntenance personnel.
The health physics technfcfan and Fire Srfgade coaposftfon say be less Chan the afnfeu requfreoents for a perfo4 of tfae not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, fn order to accommodate unexpected
- absence, provided feeedfate action fs taken to fill the required positions.
ST.
LUCIE NIT 2 6 1
Onsite and Offsite Or anization 6.2. I 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.
Liges of authority,'esponsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.
Those re-lationships shall be documented and updated, as appropriate, in the form of organizational charts.
These organizational charts will be documented
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I b.
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 s
continu nu ar safety is assured.
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for overall unit safe operation and shall have control over those onsite resources neceasary for safe operation and maintenance of the plant.
d.
Although the individuals who train the operating staff and those who carry out the quality assurance functions say report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.
e.
Although health physics individuals may-etport to any appropriate manager onsite, for matters relating to radiological health and safety of employees and the public, the health physics manager shall have direct access to that onsite individual having responsibility for overall unit management.
Health physics personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.
0 ADMINISTRATIVECONTROLS UNIT STAFF (Continued)
Adequate shift coverage shall be maintained without routine heavy use of overtime.
The objective shall be to have operating personnel'ork a normal 8-hour day, 40-hour week while the plant is operating.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance or major plant modifica" tion, on a temporary basis the following guidelines shall be followed:
a.
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.
b.
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.
c.
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.
. d.
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 by the Plant Manager or his deputy, or 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.
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ST.
LUCIE " UNIT 2
/
6-2
AOMINISTRATIVE CONTROLS MEETING FRE UENCY 6.5. 1.4 The FRG shall meet at least once per calendar month and as convened by the FRG Chairman or his designated alternate.
QUORUM 6.5.1.5 The quorum of the FRG necessary for the performance of the FRG responsibility and authority provisions of these Technical Specifications shall consist of the Chafrean or his designated alternate and four members including alternates.
RESPONSIBILITIES 6.5.1.6 The Facility Revie~ Group shall be responsible for:
a.
b.
C.
d.
~
eo Review of (1) all procedures required by Spicfffcatfon 6.B and changes
- thereto, (2) all programs required by Specification
- 6. 8 and changes
- thereto, and (3) any other proposed procedures or changes thereto ai deterafned by the Plant Manager Co affect nuclear safety.
Review of all proposed tests and experfsents that affect nuclear safety.
Review of all proposed changes. to Appendix A Technical Specifications.
Review of all proposed changes or eadfffcatfons to unit systems or equipment that affect nuclear safety.
Investfgatfon of all violations of the Technical Speciffcatfons, including the preparation and forwarding of reports covering evalua-4 4 t(
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t th and to the Chairman of the Company Nuclear Revfev Board.
Sch 'dr V:w Revfev of all REPORTABLE EVENTS.
~< ~'~+ -A~clee R Review ot unit operations to detect potentfal nuclear safety hazards.
Performance of special reviews, fnvestfgatfons or analyses and reports thereon as requested by the Plant Manager or the Company Nuclear Review Soard.
Revfew of the Security Plan and fapleeentfng procedures and submittal of recommended changes to the Coepany Nuclear Review Soard.
Revfew of the Eaergency Plan and fapleaentfng procedures and subafttal of recommended changes to the Company Nuclear Review Board.
i'T. LUCIE - UNIT 2
//
6-8 Amendment No.
13
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AOMINISTRAT I VE CONTROLS RESPONS I B ILITIES (Cont fnued)
SCn e'or PrCO'YfC t-h'~d~~
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Review of every unplanned onsite release of rad)oac
)ve material to the environs
)nc1uding the ireparatfon of reports co ering evaluation, recoamendatfons and disposition of the correct)ve ac )on to prevent recurrence and the forward)ng of these reports to the and to the Company Nuclear Review Board.
1.
Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL and RAOMASTE TREATMENT SYSTEMS.
m.
Review and documentation of judgment concerning prolonged operation in
- bypass, channel trip, and/or repair of defective protection channels of process variables placed fn bypass s)nce the last FRG meeting.
AUTHORITY 6.5.1.7 The Facility Rev)ew Group shall:
a.
Reconmend fn writ)ng to thc Plant Manager approval or disapproval of items considered under Spcciffcat)ons 6.5.1.6a.
tht'ough d.
and m.
above.
b.
Render determinations fn wr)ting w)th regard to whether or not each I
item considered under Spccfffcat)ons 6.5;1.6a.
through e.
above constitutes an unrcvfewed safety question.
uud~
c.
Prov)dc written not)ffcatfon wfthfn 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the and the I
Company Nuclear Rcv)cw Board of d)sagreemcnt between the FRG and the Plant Manager; however, the Plant Manager shall have r'espons)bflfty for resolut)on of such dfsagreements pursuant to Spec)ffcat)on 6.1.1 above.
RECORDS 6.5.1.8 The Facility Review Group shall mafntafn wr)tten minutes of each FRG meeting that, at a m)nimsn, document the results of all FRG actfv)t)cs performed under thc respons)b)lfty and authority provisions of these tcchn)cal specfffca-t)ons.
Copies shall be prov)ded to the
, and the Chairman of the ompany Nuclear Review Board.
6.5.2 COMPANY NUCLEAR REVIEM BOARD CNRB FUNCTION 6.5.2.1.
The Company Nuclear Review Board shall function to provide independent.
review and audit of designated act)v)tfes fn the areas of:
a..
nuclear power plant operations b.
nuclear eng)necrfng c.
chem)stry and radfochem)stry d.
metallurgy
'T. LUCIK - UNIT 2 6-9 Amcndmcnt No. 13
APHINISTRAT IVE CONTROL 6.6 REPORTABLE EVENTS ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
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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
- FRG, and the results of this review shall be submitted to the CNRB and the S I SAFETY LIMIT VIOLATION
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pJAAC~~ I 6.7.1 The following actions shall be taken fn the event a Saf t fmf is violated:
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IJr'CC PrA IdC& PYAJCs a.
The NRC Operations Center shall be notfffed b telephone as soon as possible and fn all cases r1thfn 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The d th CNRB h ll h tltl&~tiM 14 I
b.
A Safety Limit Violation Report shall be prepared.
The report shall be revfewed by the FRG.
Thfs report shall descr1be (1) applicable
=
circumstances preceding the violation, (2) effects of the violation upon facility components.
systems or structures, and (3) corr c v
action taken to prevent recurrence.
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The Safety Lfm1t Violation Report shall be submitted t t e onefssfon, the CNRB and th w1thfn 14 days of the violation.
d.
Cr1tfcal operation of the unit shall not be reslned until authorized by the Coamfssfon.
6.8 PROCEDURES AND PROGRAI6 6.8.1 Mrftten procedures shall be establfshed, fmplemented and maintained covering the activities referenced below:
a.
The applfcable procedures recewwnded fn Appendfx "I" of Regulatory Guide 1.33,. Revision 2, February 1978, and those required for
.,implementing the requirements of NURES 0737.
b.
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d.
Refueling operations.
Surveillance and test activities of safety-related equfpment.
Security Plan feplementatfon.
e.
Emergency Plan implementation.
ST.
LUC?E - UNIT 2 P
6-13 Amendment No.
13