ML17341A893

Proposed Tech Spec 6.0 Changes Re Administrative Controls. Safety Evaluation Encl

ML17341A893
Person / Time
Site:	Turkey Point
Issue date:	02/16/1982
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17341A892	List: ML17341A891 ML17341A893
References
NUDOCS 8202220173
Download: ML17341A893 (41)

Text

6.0 AOMINISTRATIVE CONTROLS

6. 1 RESPONSIBILITY 6.1.1 The Plant Manager Nuclear shall be responsible for overall 1 icensed faci 1 ity operation and shal 1

delegate in writing tne succession to this responsibility during his absence.

6. 2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown in Appendix A of the Florida Power and Light Company Topical guality Assurance Report.

FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-1 and:

a.

Each on duty shift shall be composed of at least the minimum snift crew composition shown in Table 6.2-1.

b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

c.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

8202220173 8202th PDR ADOCK 05000250 PDR 6-1 2/16/82

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L'EFT BLANK INTENTIONALLY 6.2 2/16/82

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.'Remeq a'I 0<0';ce STAFF HEAL.h PHYSICS Qm~~h

&Cence STAFF FZRE PROTECTION ADNIitZSTRATOR FOSSIL PLANT SITE @IMAGER PLAN i~Bi&GER NUCLEAR PLANT S'CUR Y

SUPE'tVZ 0't OPERATIONS SUPE')~MTENDENT NUCLFAR

{}CA%7iiiv CONTROL SUPERVISOR TECHNICAL D PARTNEVT SUPERVISOR

'UCLEAR SAPPY COF MITT E MAINTENANCE SUPER NTEAOEM HUCLEAR L

)IEALTH PhYSICS SUPERVISOR RADIATIO)t PROTECTIOit 4&)

CHE)IZSTRY SUPERVISOR OPERATIONS SUPERVISOR NUCLEAR PLAt)T SUPERVISOR REACTOR SUPERVISO" TRAINING SUPERVISOR SHIFT TECHNICAL ADVISOR INSTRUVENT CONTROL SUPERVISOR ASSISTANT SUPERZit EiAOENT

)"EC)IA))ICAL IIAINTENANCE bl)CLEAR ASSISTANT SUPERINTEND)ENT ELECTRICAL HAZNTENANCE NUCLEAR t)UCLEAP

)thTC)t ENGINEER NUCLEAR CONTROL CEI. ~ ER 0? ERATOR

- 1. Senior Operator License

2. Operator License..

Licensed Personnel on

=--Shift as shown in Table 6.2-1 PLANT ORGANIZATION CHART

-FIGURE 6.2-I

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between the PNSC and the Plant Manager - Nuclear;

however, the Plant Manager Nuclear shall have responsibility for resolution of such disagreements pursuant,to 6.1.1 above.

6. 5. 1. 8 RECORDS The Plant Nuclear Safety Committee shall maintain written minutes of'each meeting and copies shall be provided to the head of the Nuclear Energy Department and Chairman ot'. the Company Revi ew Boar d.

6.5.2 COMPANY NUCLEAR REVIEW BOARD

CNRB, 6.5.2.1 The Company Nuclear Review shall function to pr ovide independent revi ew, and audit of designated activities in the areas of:

6. 5. 2.2 a.

Nuclear power plant oper ations.

b.

Nuclear engineering.

c.

Chemistry and radiochemistry.

d.

Metallurgy.

e.

Instrumentation and control.

f.

Radiological safety.

g.

Mechanical and electrical engineering.

h.

equality assurance practices.

COMPOSITION The composition of the CNRB shall be as shown in Appendix A

of Florida Power 5 Light Company Topical guality Assurance Report.

2/16/82

'll 1v

ALTERNATES Alternate members shall be appointed in writing by the (CNRB)

Chairman to serve on a temporary basis;

however, no more than two alternates shall participate in (CNRB) activities at any one time.

CONSULTANTS Consultants shall be utilized as determined by the CNRB to provide expert advice to the CNRB.

MEETING

~R f(RUE NCY The CNRB shall meet at least once per calendar quarter during

.the initial year of faci.li.ty operation

.fol,lowing fuel loading and at-least once per six months thereafter.

(PORUM A quorum of the CNRB shall consist of the chairman or designated acting Chairman and tour (4):members including alternates.

No more 6-10 2/16(82

SAFETY EVALUATION There are no safety related effects connected wi th the removal of the offsite management and technical support description and organization charts from the Technical Specifications.

The purpose of including these descriptions is for general information and the corporate structure to those in possession of the Technical Specifications.

However, this same information is also contained in the Florida Power 5

Light Company Topical guali ty Assurance report (FPLTgAR).

Me supply controlled copies of the FPLTgAR to at least the same non-FPL organizations as receive controlled copies of the Technical Specifications.

The FPLTgAR is required to be updated to reflect all changes to the organization which affect quality within 30 days by letter and one year by amendment.

It is our opinion that duplication of material between the two documents is unnecessary and that processing the same change twice is an uneeded burden on the. time and manpower resources of both FPL and the NRC.

Should the need arise for information on the organization, the FPLTgAR will be available to the same people who previously would have had the organizational description in the Technical Specifications.

In a similar fashion the composition of the CNRB is duplicated in both the Technical Specifications and FPLTgAR.

For the same reasons as stated

above, we propose to remove the specific composition of the CNRB from the Technical Specifications.

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6-0, ADMIHISTRATIVE HTROLS wt W~

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6.1 RESPONSIBILITY

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6.1.1 The Plant Aanager - Nuclear shall be responsible-for ov licensed facility operation and shall.delegate. in writi succession-to thi's =responsibil ity during his absence.

eral 1 ng the 6.2 ORGAN IZATION 6.2.1 OFFSITE The offs'ite organization for.facility management and technical support shall be shown on Figure 6.2-1.

6.2. 2 FACILITY.STAFF The Facility organization shall be as shown on Figure 6.2-2' and:

a'.

Each. on duty shift shall be ccmposed of at least the minimum shift crew composition shcwn in Table.6-2-1.

b.

At least one licensed Operator shall be in the control rocm when fuel is in the reactor-c-

At least two licensed Operators shall be presert in the control rocm during reactor start-up, scheduled reactor

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shutdown and dur ing recovery.frcm reactor.,trips.

6-1

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Amendments 6&'&'8 thAY y 3 )gg)

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KIKCVIIVE TICE tIKS IDENT I

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TICE tlKSI DENT ADVANCED ST5TEHS AND TECHNOLOGY J

TICK tlES IDENT 40'MEI IKSOVICKS TICE tlKSIDKNT

~ FUEL'ESOUICES I COltOIATE DETELOtHENT COHFANT NVCLEAA IETIKM 40AID CZ 7%ftl PC I IIKCTOI XXCLKII AfF AIIS OIIKCIOI EXT I IOHmaurAL AfFAIAS KANAOKI OMEI IESOVICE

NllCLKAI, NANACKI to'IKI IKS441CE IIIIICE'I I

HANAGEI ~

NUCLEAI ANALTSIS s

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XANACEI 40ALITT ASSOIINCE 5ITK

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. HANAGKI tOMKI AESOVICES NVCLEAI SEIYICKS tOMEI IESOUICKS STAFF NUCLEAI CNIKF ENGINKEI tOMEI tLAN'f ENCINEEIING I

SEE FIOUIE Oel 2 CONTINVKO OX FICVIE 4 ~ 2 2 4

INCLUDES MEAON tNT5I C5 IADIOCMKHISTII, FLINT SVttOITi flIE tlOTECTION ADHINIStlATOI, KHEIGENCl FLANIIXO, ETC,

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~ o2-I OffSITE OIDANIlATIONfdl FACILITY HANACKHK

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I POHER RESOURCES STAFF HEALTH PHYSICS

)IrrzA m FIC. 6.2-1 POHER RESOURCES STAFF

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FIRE PROTECTION ADHItlZSTAATOA REFER TO FIG. 6.2 1

FOSSIL

~PLANT SITE HANACER PLAIIT HAHACER WCLEAR

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PIJQIT SECUAITY SUPERVISOR s

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OPERATIONS SUPERI NTEtiDEIIT WCLEAR' QUALITY COIITAOL SUPERVISOR TECIIIIICAL DEPARTHEtlT SUPEAVISOR

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'CLEAR 6APETI

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)UIIIITEIIhtiCE SVPERI IITLIIDEHT ttUCLEAR '

1)EALTII PHYS IC6 SUPEAVI6OR CHEHISTRY SUPERVISOR OPEIIATIOHS SUPERVZSOA REACTOR

'VI'ERVISO THAI II INC 6UPERVISOR I

SNIFT TECHNICAL ADVISOR I:

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INSTRUHEHT ti COIITROIs SUPERVISOR ASS I6TAHT SVPERINTEIIDEHT HECNAHICAL

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ASSISTANT

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SUPERIHTEIIDRiT ELECT A ICAL HAIIITEIIAIICE NUCLEAR RADIATION PAOTECTZOII HAH IIUCLEAR PLhtiT SUPERVISOR s

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NUCLEAR HATCII EHCItlEEA 1

NUCLEAR COslTROL CENTER OPERATOR 4

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s TABLE 6.2-1

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MINIMUM SHIFT CREW COMPOSITIONP.

a

,I LICENSE CATEGORY"-..

One or OUALIFICATIONS... Twn Units Operating All Units Shutdown SRO*

2 RO Non-Licensed Auxi1 iary Operators.

--3..

Shift Technical Advisor 1

None Required This'position may be filled by one. of the SRO's abo~e, provided the

,individual, meets. the qualification requirements of 6.3.1'-

Incl.des the licensed 'Senior Reactor. Operator serving as. Shift Supervisor.

P Ooes not include the licensed Senio~ Reactor Operator or Senior Reactor Opera or Limited'o Fuel Handling, supervising the movement of any component within the reactor presssure,vessel with the vessel head removed and fuel in the vessel.

Operating is defined as Keff > 0.99;

~ thermal power exc',uding decay heat greater.than or equal to zero, and an average coolant temperature Tavg

-> 200 F-Siiift crew ccmposition may be one'less than the minimum requirments

-,or, 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 accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to res.ore the shift crew composition to within the minimum requirements of Table 6.2-1.

This provision does not permit any shift crew position to be unmanned. upon shift change due to an oncoming shi t crewman being late or. absent.

Amendment Nos.

70 5 63

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6-3.1 d.

An individual qualified in radia ion. proiection procedures shall be on site when fuel. is in the reactor.

e.

ALL CORE ALTERATIONS shall be directly supervised. by either a

licensed Senior Reactor Operator or Senior Reactor Operator Limited"-to Fue1 Handling.who -has no other, concurrent'.--.

respons'ibi1ities during this oper'ation.

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A'. 1east:.Qree.

(3) persons shill be maintained on site;at.al-l times-for Fire Emergency response.--.

Thgs exit.udes two (2) menbers of, the shift crew.:=a-6.3 FACILITY STAFF-'ALIFICATIONS.----.--

.-.- -,;- - ~ --. ~ ~--

Each member of the faci1i.ty staff shall meet or exceed the minimum

'ualifications'of ANSI N18.1-1971.for comparable positions.

except for the Shift:.Technical Advisor who. shall~ have a.bachelor's degree or..

.'equivalent in a-scientific or engineering discipline with specific

.training in plant.design 'and in. the response and analysis.af Che plant for transients and accidents'-.:-

6.3.2 HEALTH PHYSICS'UPERVISOR QUAL'IFICATIONS=

6.3.2.1.

The Health Physics Supervisor at. the. time of appointment to the..

position; shall; except as'ndicated beIow; meet the following:

1.. He shall have a bachelor's degree ~r equivalent in a science or engineering

subject, including some =ormal traini ng in,radiation protection..

2.

He shall have five years of professional experience in applied radiation protection; where a master's degree in a related field.

is equivalent to one year experience and a doctor's degree in a

related field is equivalent to two years of exoer ience.

3.'Of his ive years o

experience, three years shall be in applied radiation protec ion work in a nuclear facility dealing 'with radiolog;cal problems similar to those encoung red at Turkey ?oint Plant.

6.3.2.2.

When the Health Physics Supervisor does not meet, he above requirements, compensatory action shall be taken which the Plant Nuclear Safety Committee determines, and he NRC 0 fice of Nuclear Reactor Regulation concurs that the action'e ts the intent of Specification 6.3.2.1.

6.4 TRAINING

6. 4.1 A retaining and replacement program =or the,acility staff shall be maintained under the direc~ion of..the Training Supervisor and shall meet or excel'e requiranents and recanmendaCi9as of Section 5.5, ANSI N18.1-1971 and Appendix A.to 10 CFR Part 55.

'6-5 Amendment Nos.

70 L 63

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6 4-2 A training program for the Pire Emergency response members shall be maintained under the direction of the Fire Protection.

Administrator and should meet or exceed the requirements of..

Section 27 of the NFPA Code-1975, except for fire'Brigade'raining sessions which shall be he1d at. least quarterly 6-5 REVIEvT AND AUDIT.

6.5 1

6-5.1.1 Plant Nuclear Safety Committee (PNSC)

FUNCTION The PNSC shall. function to advise the Plant all matters related to nuclear safety.

Managez;-Nuclear on

'.5.1-'2 COMPOS ITION The Plant-Nuclear Safety'ommittee shall,be

l. 'hairman Plant Manager - Nuclear composed of the:

2 Vice Chairman:

. Operations Superintendent 3.

Technical 'Department Supervis'or 4.

Maintenance Superintendent Nuclear 5.

Instrument and Control Supervisor

<< Nucl.ear 6.

Health Physics Supervisor 7.

Reac tor Supervisor 6.5 1.3'LTERNATES V

Alternate members shall be appointed in'riting by the PNSC Chaiman to serve on a temporary basis; however, no more than two alternates, shall participate in PNSC activities at any one time.

6 '

1.4 MEETING EREOUENCY

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The PHSC shall meet at least once per calendar month and. as convened by the PNSC Chairman.

Amendments 6'6 5 58 6-6

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6.'5.

1 6.5.1

.5 QUORUM A quorum of the PNSC shall consist of the Chai'rman or Vice Chairman and four (4) members including alternates.

. 6 RESPONSIB ILITIES The Plant Nuclear Safety Committee shal,l be responsible for:

a. '-'.. Reyi 6w-.'of -1). all - procedures -.and: changes

.thet eto -required by Sect~on 6.8 and.2).-.any other.

proposed procedures

.or changes..

--'hereto as determined.by=the Plant.Hanager:-

Nuclear.-.te:. '

"-affect: nuclear safety.

6.

Re'view of all 'proposed..tests and experiments that affect nuclear safety..

,c.. Review of all proposed changes to the Technical Specifications in Appendix A of the license.

d.. Review-'of al 1 'proposed. changes

.or. modifications.to, pl ant.

systems or equipment that affect nuclear safety.

e-Investigation xr'f-al 1-violations of the. Technical Specifications and preparation and forwarding a report

'covering evaIuation. and recommendations to prevent

recurrence to the llanager of Power Pesources - Nuclear,'o the Yice President of, Power Resources and to the Chairman of the Company Nuclear Review 8oard.

'mendments 66 & 58 6-7 ViAY 12 B8>

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,S 6-5-1 ~ 7 f.

Review of facility operations to.detect potential safety hazards-g.

Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Company Nuclear Review Board..

h.

.Review. of the Plant Security Plan and.implementing.

procedures arid submitting reccmmended changes to the Chairman of the -Company Nuclear Review.Board.

Review of:the Emergency Plan.and implementing procedures and submitting recommended changes to the Chariman of the Company Nuclear Review Board.

AUTHORITY The Plant Nuclear Safety Committee shall:

E a.

Recommend to the Plant Manager - Nuclear written approval or disapproval (in minutes of PNSC meeting) of itens considered under 6.5.1.6'(a) through (d) above.,

b. 'ender det'erminations in wr iting (in minutes of PNSC meetings).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 immediate-written notification to 'the Yice Pres~dent - Power Resources and the"Company Nuclear Review

= Board of. disagreement

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Amendments 66 & 58

-.. trav >2 BBi 6-8

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~z between the PNSC and the Plant Manager - Nuclear; however~

the Plant

~fanager - Nuclear shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above 6-5.1-8 RECORDS I

.The Plant nuclear Safety Committee 'shall maintain written"."-

minutes.of.'ach meeting. and. copies shall be provided to the Vice Presiden't' Powei Resources

'and Chairman of the Company eview Board 6 5.2 COMPANY NUCLEAR REVXEV BOARD (CKH

6. 5-2.1

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h PUNCTTON The Company independent areas of:

a.

Nuclear Nuclear R'eview Board shall function to provide review and audit of designated activities in the P

power plint operations b.. Nuclear engineering.

c.

Chemistry and radiochemistry.

d'etallurgy.

e.

instrumentation and co Radiological safety.,

ntrol V

g., Mechanical and e1ectrical engineering-h-

Quality assurance pra'ctices5.2.2 COMPOS'ZT TOH.

The CNRB shall 'be commposed of the:

Amendments 65 8 58 6-9

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1 Chairman:

Vice President - Advanced Syqtems and Technology 2.

Member:

Chief Engineer - Power Plant Engineering 3-Member Vice President - Power Resources 4..

Member:

.. 2fanager of Power Resources - Nuclear 5-Member:

Director of Nuclear Affairs 6-Member:

7-Member:

Power Plant Engineering Manager Power Plant Engineering supervisor 6.$. 2-3 ALTERNATES Alternate members shall be appointed in writing by the (CNRB) Chairman to serve on a temporary basis;

however, no more than two alternates shall participate in (CKK) activities at any one time..

652.4 CONSULTANTS Consultants shall be utilized as determined by the CNRB to provide expert advice to the CNRB..

6 5.2.5 MEETING 'PRE UENCY 6-5.2.6

~ The CNRB shall meet at least once per calendar quarter".

during.the intial year of facility operation following fuel:

loading and at 'least. once per s&c months thereafter.

Jt CIUORUM A, quorum of the'CNRB shall consist of the Charon or designated acting Chariman and four (4) members including alternates.;Ho more Amendments 68 5 58 6-1 0

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'peration of the f 'iity.

>a ~alsf lldvG i.kllc Jc 0/vol>4.allJ i@7 lvl R~Vl>

'he CNRB shall review:

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Thc safety evaluation" ior 1) changes to procedures, equip. cnt J'r systc;..s

.and<

2) 'ests or cxpcri~cnts completed'nder thc pr--

vision of Section 50.58,

.10 CFP., to ver'fy that. such action die not constitute an unrcviewed safety question,

~

'roposed.

changes to procedures, equi)rent or systcr.

which in-volvc an unreviewcd safety question as defined in Section 50.59,

.10 CFR; c,

Proposed test".or'xpcrimcnts which involve an unrcvicwcd safety.

question as defined in Section'0.59, 10 CFR.

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d.

-Proposed changes in Tcchnical Spccif ications or Licenses.

e.

Violations of applicable statutes,

codes, regulations,

orders, Technical Spccif'ications, license requirements, or of internal pro-cedures or instructions having'uclear safety significance.-'

f..

~ Significant. operating abnor;..alitics or deviations from normal and

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expected performance of plant equipment that affect nuclear safety g

~1 events which are required by regulations or Technical Specx&catfons to be reported'o the NRC in smiting ii'ithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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Any inMca ion o u~ticipated. deficiency

.so-'spect, of desim or operation of safety'eland. smzctums, systems J or components.

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RepoM and meeti"~ ut u~s of th Plant Nuclea Safety Co~~ttee, 6.5.2.8 A'JETS

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A~ts of facility acti&ties sM~ be pez omeC under th co~~~ce of the.~.

These a))its shall encompass:

~'I The confo~ce of faculty opera ~on to all pm&sions con~~ t -Wt4'~ the TecM~cal S eM~i.cations an~ app<<cable

,license co~2.ons at least once pe year.

The po once, ~~~g ark om~M~ica ions of ~De en~tw facility s~~f a leas.

once per yea c.

The, results. o a~ ~ actions. taken to correct deficiencies ocean.mg in ="acuity equipment, s ct~s, system or'..

method. of operon tat a feet "uclear sa ety zt least 'once) six ~n~ ~

'he pe~once oz all ac~ZWties mg~~d. by.t¹ guz3~ty Ls-'~ce.Mc~ to me t the criteria of Append~~.-"3" iO M g, a.

1 ast once.per t~o years.

e.

TM~:--e~~~ P~~ an" ~~3.emen~~

p~mcedums at least once p m yea~.

f.,

T>

-" ~~r Flan arL implemen~+,procedures at least once pe

~~0 ye?

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g.

The Fac&ity Fire at least once per Protection Pro~am and. fzmlementing procedures two years.

Amendment No.

42 Unit 3 Amendment No 34 Unyt 4 ttOV 8 m

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independent e protection and loss preven n'inspection and audit shall be performed annually. uti3;izing.either qualified licensee personnel or an outside fixe protection.firm.

An-inspecpion and audit of the fire protection and loss prevention program shaM be performed by an outside qualified fix'e consultant at intervals no greater than three (3) yearC.

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Any other..-areaxof-facility.operation: consCBereB apjiopriate by the CNRS or the Executive Vice President.

6.5.2.9

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QQT ~j W~K3 s>~~". xeno~ to and. ECse

~se a~as oL res~

bh~i y spec'e" Exocnt<<ve-Vice ~sid

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M Sec 'oa 6 5 2 7 ~'6 5 2 8

- 6.5.2.10 Zeco=m o

Qt-~ zc&v <<s s~~

be pz ~,

a, proveL ~ d<<s~trgm~

1 aa ~~-'c-m" belo-~"

v a.

5~uws of'zch CliB meetiag s}~ be p~~d, appmveQ. a-<

fo~~m" u t>e Wecutive Vice pmsid~nt v'~ fog~~~m dzys

~cZZo~ e~ch meeting.'

r Peyote of ~Mews encorxzssel

.by.Sec

<<on 6.5.2.7.e',,'g a-Q. g s M be g Bjc

=d.~

KDg ove( KL>> fo~~a ~d w ~.e Qec>>~vp 7'

~sice" w~tM four&en czys folio@~ cot;pletio" of

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Ce z ~~s encompassed.'by Sec~<<on 6.5.2.S zbove, s'."-~~ be

-."o;~~ to the Executive Vice Presides-az;i m the ~~~e en%,

='o"s

~r ible

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coapletion for tre z

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endment No.

42 U1t 3 NB< 8

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'Amendment No'4

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6.6".

g. ~-l pz Op~s~L QC<rz~~t;Ct'C.IQ't 1

T¹ follow~~".~ action

?~~1 be ta'-en in t¹ even a B:-PORT~LE CCCUnP='~-

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T¹ p==ORT~L-QCC'~<- fC=- s?al~

be'zepo~~ud.. to

~he Con~sion.

he -cpu>> zem n m of Sect>> on 6.9.

h, Repox able Occ~nce Report s~

be prepared..

The r pox shall be reviewed..by the l'last Nucl az Safety Coamd.ttee.-

T¹ Repoz able Occv~nce Repoz shall be submitted.

m the C~

the Vice Pws~den+

b iot'e~ Resouzces, and.

ne Cow?Ssion C~

the ~e a13.otter. in Sec 'on 6.9.

6.7 6;7.Z S~~~

LIMITVIOLA~~Oh

~~w fo32os~ a.c>>ow s?M be take.". M the eve"

a. m~eQ ~t is

. viola d.:

~,pmvisions.of 10 ~z 50.36(c)(l)(i) s~ be compUed. W>>~

~e~tely.

b.

The Sa~

v ~>>" t violation s?~

be reported. ir".ed'ately to the Co=->> sion,

?

Yic ~siren of. Paver R sou=es an" to the C'~~~... --".-

c.

A Sa e~ ~+ Violat'on Report shalL be prepaz d..

The report'~~~

be rev>>e~ed. bv the ElSC.

TtJ.s'epo~~ shall desMbe f) applica>>

ci=~taz:ces pzecedin> the vio3~ Don,') '<fecm 3:e w+olation u>on fa.cility compo." r.ts,. systems or'tzuctu~s,

. a"d. 3) co~cti~ action taken to prevent ~cu~nce..

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~~-"e+ X~"'t V>>mlation Report shaZl be submitted. to the

.CF3,

. '"a V5.ce Wsident of Power R sou=es asC th Cow<&on wit?~ ~ (~0) days of the violation.'

s'.".0~i.r=S Written procedures and administrative policies shall'e established, implemented and maintaihed that. meet or exceed the requirements and.

0 recomendations-of Section 5.1 and 5.3 of ANSI N18.7-1972,. Appendix "A" of USNRC Regulatory Guide 1-33, 'and the Facility Fire Protection Program

- except as provided in 6.8.2 and 6.8.3 below.

This requirement shall be

'mplemented within four (4) months from the effective date of this amendment.

Ameridment No. 42 Unit 3 A

ndment No.

34 Uxt 4 gag Q

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6. 8.2 Each procedure and administrative policy. of 6-8.1 above, and changes

thereto, shall be revieved by the PNSC and approved by.

the Plant Manager Nuclear prior to implementatiqa and periodically as provided by procedure.

6-8. 3.

Temporary changes to procedures of 6.8.1 above may be made provided:

a.

The intent of the original procedure is not altered.

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b.

The change is approved by two members of the plant management staff, at least one of Qiom holds a Senior.

Operators License on the unit af fected.

c The change is documented, revieved by the E5SC and approved by the Plant Manager Nuclear within fourteen days of.

implementation 6-1 5 Amen,dments 66 5 58

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