Text

Proposed Tech Specs,Changing Word Data to Date in 6.10.3,adding Radiation Protection to List of Assessments Performed by Nuclear Assessment Section in 6.5.4.2 & Rewording 6.5.3.4
	ML18011A821
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Site:	Harris
Issue date:	03/06/1995
From:	; CAROLINA POWER & LIGHT CO.
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ML18011A820	List: ML18011A819; ML18011A821;
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ENCLOSURE 4 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT PERFORMANCE BASED NUCLEAR ASSESSMENT PROGRAM TECHNICALSPECIFICATION PAGES nhnsdlnls'eri>ad21$.tsc 9503i30088 950306 PDR ADOCK 05000400 P

PDR L

INDEX

6. 0 ADMINISTRATIVE COHTROLS SECTION P.AGE

6. 1 RESPOHSIBILITYo ~

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6. 2 ORGANIZATION..............'...

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6-1 e.2.1 oHSITE AND oFFSITE......................................

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.2.2 UNIT STAFF..........;............-........

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6-1 6-3 FIGURE 6.2-2 DELETED...................

6"4 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION....................

6-5 6.2.3

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6-6

6. 2. 4 SHIFT TECHNICAL ADVISOR...................

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6 6.5 REVIEW AND AUDIT...........................-.....

6-7 6-7 6.5.1 SAFETY AND TECHNICAL REVIEWS General Program Control....................;..............

6-7 T

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t echnlcal Evaluatlons................................-....

6-7 Qualified Safety Reviewers............................

6-7 Safety Evaluations and Approvals...

e.5.2 PLANT NUCLEAR SAFETY COMMITTEE (PNSC) 6-8 FunCt1 On ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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eetlng frequency...............................'.......~..

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Lo1 oa esponslbl l 1tles......................... -....... - -......-

Records

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6-9 6-9 6-11 SHEAROH HARRIS " UNIT 1 XV111 Amendment No. g

INDEX ADMINISTRATIVE CONTROLS SECTION PACE NUCLEAR AEENSSIAEMT SE<TIDQ ZdbEPNMDENT @VIE< PRIXIRAM 6.5.3 FunC't10n

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6"12 6.5.4 NtlCMAR AMGSS&lGAIT EC7/bN

>SSSSS~EV7 Pgmug 6-13

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6.5.5 OUTSIDE ACENCY INSPECTION AND AUDIT 'PROCRAM... ~. ~

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o 6.7 SAFETY LIMIT VIOLATION.~ ~ o.

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6.9 REPORTINC RE UIREMENTS.

6-16 6.9.1 ROUTINE REPORTS.

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6-20 Startup Report.................

6-20 Annual Reports..........

Annual Radiological Environmental Operating Report.

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Core Operat1ng L1mits Report................................

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SPECIAL REPORTS'

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6-20 6-21 6"22 6-23 6-24 6-24 6-24 6oll RADIATION PROTECTION PROGRAM.

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6"26 F 12 HIGH RADIATION AREA.. ~ ~ ~. ~ ~ ~ ~. ~ ~ ~ ~ ~ ~ ~ ~ ~

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6-26 6ol3 PROCESS CONTROL PROGRAM (PCP)

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6-27 SHEARON HARRIS - UNIT 1 X1X Amendment, No.

ADMINISTRATIVE COHTROLS 6.2.3 NCTIOH 6 ~ 2.

The PA Section shall function to examine unit operating characce

'scics, HRC issuances, induscry advisories (including informacion forvarded INPO from their evaluation of all industry LERs),

and other sources of 'un design and operating experience informacion, including unics of similar desi Mhich may indicate areas for improving unit safety.

The PA Section shall make etailed recommendations for revised procedures, equipment modiEications, mainte nce activities, operations activities, or ocher means of improving unit safec co appropriate levels of management, up co and including che Executive Vi President - PoMer Supply, if necessary.

COMPOS ITIOH 6.2.3.2 The PA Seccion shall include c least five, dedicaced, Eull-time engineers 1'ocated on sice.

Each shall h

e a baccalaureace degree in engineering or related science and at leas years professional level experience in his field, at least 1 year of M

ch experience shall be in the nuclear field.

RESPONSIBILITIES 6.2.3.3 The PA Section shall be responsible Eor majntainin surveillance oE unit activities to provide independent verification chat the activities are performed correctly and that human errors are reduced as much as ractical.

RECORDS 6.2.3.4 Records of activities performed by che PA Section shall be prepare maintained, and EorMarded each calendar month to the Manager - Nuclear Assessment Deparcmenc.

6 ~ 2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the ShiEt Foreman in the areas of thermal hydraulics, reactor en'gineering, and plant analysis Mith regard to the safe operation of the unit ~

The Shift Technical Advisor shall have a baccalaureace degree. or equivalent in a scien-tific or engineering discipline and shall have received specific training in che response and analysis of the unit for transients and accidents, and in'nit design and layout, including che capabilities oE instrumentation and controls in the control room.

6.3 Deleted

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Rot responsibie for sign-off function.

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SHEARON HARRIS - UNIT 1 6"6 Amendmenc Ho.

ADMINISTRATIVE CONTROLS ual ified Safetv Reviewers (Continued)

These'ndividuals shall have a baccalaureate degree in an engineering or related Eield or equivalent, and 2 years of related experience.

S~. h designation shall include the disciplines or procedure categories Eor which each individual is qualified.

qualified individuaLs or groups not on the plant staff may be reLied upon to perform safety reviews if so designated by the Plant General Manager.

6.5.1.4 Safet Evaluations and Ao rovals 6.5 ~ 1.4.1 The safety evaluation prepared in accordance with Specification 6.5.1.1.1 shall include a written determination, with basis, of whether or not the procedures or changes

thereto, proposed tests and experiments and changes

thereto, and modifications constitute an unreviewed safety question as defined in Paragraph 50.59 of 10 CFR Part 50, or whether they involve a change to the Final Safety AnaLysis Report, the Technical Specifications, or the Operating License.

6.5.1.4.2 The saEety evaluation shall be prepared by a quaLified individual.

The saEety evaluation shall be reviewed by a second qualiEied individual ~

6.5.1.4.3 A safety evaluation and subsequent review that conclude that the subject action may involve an unreviewed safety question, a change to the Technical SpeciEications, or a change to the Operating License, will be referred to the PLant Nuclear Safety Committee (PNSC)

Eor their review in accordance with Specification 6.5.2.6.

If the PNSC recoamendation is that an item is an unreviewed safety question, a change to the Technical Specifications, or a change to the Operating License, the action will be referred to the Coamission for approval prior to 'implementation.

Implementation may not proceed until after. review by the Nuclear Assessment SQ.C. bioN 6.5.1.4.4 lf a safety evaluation and subsequent review conclude that the subject action does not involve an unreviewed safety question, a change to the Technical Specification, or a change to the Operating License, the action may be approved by the Plant General Manager or his designee or, as applicable, by the Manager of the primary functionaL area affected by the action.

The individual approving the action shall assure that the reviewers coLlectively possess the background and, qualification in all of the discipLines necessary and important to'he speciEic review for both safety and technical aspects

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< ~4~ Vo.c.l Li~y a.s dascr'A 6.5.1.4.5 A safety evaluation and subsequent review that conclude that the a change~in the Final Safety Analysis Report shaLL be referred to the Nuclear Assessment Eor review in accordance with Specification 6.5.3.9, but impleme ation y proceed prior to the completion of that review.

Sec:Ti oH wodigicgs04s Pfo<QIGfls, tQsfs Qf'xpo~'i~~iis dkl c.ll 63~5l I t'QTQ.

6.5 '.4.6 The individual approving the procedure,

tests, or experiment or change thereto shall be other than those who prepared the safety evaluation or performed the safety review.

SHEARON HARRIS - UNIT 1 6-8 Amendment No.

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Conc inued) b ~

Review of all proposed tests and experiments char. aEfect nuclear safecy and that have been inicially determined co appear to consci-tute an unreviewed safety question or involve an unreviewed change co the Technical Specifications; c ~

Review oE all propo'sed changes to Appendix "A" Technical Specifications',

d ~

Review oE all pzoposed changes or modiEicacions to unic systems or equipment that. affect nuclear safecy and that have been initially determined to appear to constitute an unreviewed safecy question as defined in 10 CFR 50.59 or invoLve a change to che Technical SpeciEicac,ions e.

Investigation of all violations of the Technical SpeciEications, including che preparation and forwarding of reports covering. evalua-tion and recommendations to pzevent recurrence, to the Vice President.- Harris Nuclear P

PL

~T E.

Review of all REPORTABLE EVENTS; g ~

Review of unit operations to detect potential hazards to nucLear safety; h.

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Performance of special

reviews, invescigacions, or analyses and zeports thezeon as requested by che Plant General Manager or the Manager - Nucleaz Assessmenc ~~aeacr SQ,Curio H Review of the Secuzity Plan',

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Review of che Emergency Plan; k.

Review of any accidental, unplanned, or unconczoLled radioactive release including the preparation of reports covering evaluation~

recoazsendations, and disposition of che corrective action to'revent recurrence and the Eorwarding oE these reports to the Vice President - Harris Nuclear Review, prioz to implementation, of changes to the PROCESS CONTROL PROCRAM, the OFFSITE DOSE CALCULATION MANUAL, the Radwaste Treatment

Systems, and the Technical Specification Equipmenc List, Program.

6.5.2.7 The PNSC shall:

a.

Render determinations in writing wich regard co whecher or noc each item considered under SpeciEication 6.5.2.6a.

through e. cor.stituces an unreviewed safety question; and SHEARON HARRIS. - UNIT l 6-l0 Amendmenc No

ADMINISTRATIVE CONTROLS RESPOHSI BILITIES

( Cont inued) y PLaat.

b.

Provide Mrittegnotification Mithin 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President-Harris Huclear ~~

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oE disagreement betMeen the PHSC and the Plant Ceneral Manager.

However, rhe Plant General Manager shall have responsibility Eor resolution of such disagreements pursuant to Specification 6.1.1 RECORDS 6.5.2-B The PHSC shall maintain Mritren minutes of each PNSC meeting that, at a minimum, document the results of all pNSC activities performed under the responsibility provisions of these Technical SpeciEications.

Copies shall be provided to the Vice President - Harris Huclear A~.- and the Manager "

Se&i'od g~ y.o~

FUNCTION SecffoA independent revieM of plant changes,

tests, and procedures; verify that REPORTABLE EVENTS are investigated in a t,imely manner and corrected in a manner that reduces the probability of recurrence of such events>

and detect trends that may not be apparent to a day-to-day observer.

ORGANIZATIOH 6.5.3.2 The individuals assigned responsibility Eor independent revieMs shall be technically qual'ified in a specified technical discipline or disciplines.

These individuals shall collectively have rhe experience and competence required to revieM activities in the following areas.

a.

Nuclear pouer plant operations, b.

Nuclear engineering, c.

Chemistry and radiochemisr.ry>

d ~

Metallurgy, 4 Instrumentation and control,

'I~

Q Radiological safety, g.

> Mechanical and electrical engineering,

< Administrative controls, J ~j~ i~c ogJ Qggt f o ~ ~l N~)

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< Quality assurance practices>

C Nondestiuctive testing, and L Other appropriate fields, SHEAROH HARRIS - UHIT 1

6-11 Amendment Ho-26

AOHIHI STRATIVE COP%tOI.S ORCAHI"ATIOH (Continued) 82,cTi 04 6.5.3.3 The Hanager Nuclear Assessment ~a+a~~

shall have a

degree in an engineering or related field and, in addition, shall have a minimum of 10 years'elated experience, of which a minimum of 5

years shall be in the operation and/or design of nuclear power plants.

Qc.le.Lc,r

~ inJiqigea.h PCllo<ming 6.5.3.4 The lindependent safety revie S

shal 1 have a

degree in an engineering or related field or equivalent and, in addition, shall have a minimum of 5 years'elated experience.

Sec7i aP 6.5.3.5 An individual may possess competence in more than one specialty area.

IE suEEicient expertise is not available within the Huclear Assessment competent individuals from other Carolina Power 6 Light Company organizations or outside consultants shall be utilized in performing independent reviews and investigations.

6.5.

.o d?vl ua i

q E

ed in Specifica-tion 6 5.3.2 above shall review each a

the requirements oE gpPj~

u '7"p Al~ g.~. p.g (p 7"tmAed.

6.5.3.

7 Independent safety reviews shall be performed by individuaLs not directly involved with the activity under review or responsible for the activity under review.

Secs aH 6.5.3.8 The Nuclear Assessment ~~as'ndependent, safety review program shalL be conducted in accordance with written, approved procedures'.3-9 The Nuclear Assessment Department.

shall perform reviews of the Eol ing..

a ~

itten safety evaluations Eor all procedures and programs z'equired, by ci fication 6.8 and other procedures that aEEect nuclear safety and cha es thereto, and proposed tests or experiments and proposed modiEicati

, any of which constitute a change to the Final Safety Analysis Repor Implementation may proceed prior to completion of the review, b ~

C ~

ALL procedures and progr required by Specification 6.8 and other procedures that affect nucl safety and changes thereto that con-stitute an unreviewed safety qu ion as defined in Paragraph 50 59 of 10 CFR Part 50 or involve a cha to the TechnicaL Specifications; All proposed tests or experiments that constr' an unreviewed safety question as defined in Paragraph 50.59 of CFR Part 50 or involve a change to the Technical Specifications prx to implemen-

tation, d ~

ALL proposed changes to the Technical Specifications and Opera License; SHEARON HARRIS - UNIT 1

6-12 Amendmeat No.

Zg

INSERT TO PAGE 6-12.

The documents submitted under 6.5.3.9 shall be reviewed by individuals meeting the requirements of 6.5.3.2 and 6.5.3.4 to ensure disciplines are encompassed.

Multiple reviews will be conducted on documents where required to meet applicable disciplines of 6.5.3.2.

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INSERT TO PAGES 6-12 AND 6-13.

6.5.3.9 REVIEW The Nuclear Assessment Section shall perform reviews of the following:

Written safety evaluations of changes in the facility as described in the Safety Analysis Report, changes in procedures as described in the Safety Analysis Report, and tests or experiments not described in the Safety Analysis Report which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1).

These reviews are to verify that such

changes, tests, or experiments do not involve a change in the Technical Specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2).

These reviews may be conducted after appropriate management

approval, and implementation may proceed prior to completion of the review.

Proposed changes in procedures required by these Technical Specifications.

proposed changes in the facility, or proposed tests or experiments, any of which involve a change in the Technical Specifications or an unreviewed safety question pursuant to 10 CFR 50.59 (a)(2) prior to implementation.

C.

Proposed changes to the Technical Specifications or this Operating License prior to implementation.

d.

Violations, deviations and REPORTABLE EVENTS, which require reporting to the NRC in writing, such as:

1.

violations of applicable

codes, regulations,

orders, Technical, Specifications, license requirements or internal procedures or instructions having safety significance, 2.

significant operating abnormalities or deviations from normal or expected performance ofplant safety-related structures, systems, or components, and e.

3.

REPORTABLE EVENTS as specified in 10 CFR 50.73.

Allrecognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

Any other matter involving safe operation ofthe nuclear power plant that the Manager

- Nuclear Assessment Section deems appropriate for consideration or which is referred to the Mahager - Nuclear Assessment

Section, by the on-site operating organization, Plant Nuclear Safety Committee (PNSC) or by other functional organizational units within CPBcL.

2228nt i.717

INSERT TO PAGES 6-12 AND 6-13 (CONTINUED).

RECORDS 6.5.3.1 0 Results of Nuclear Assessment Section independent safety reviews shall be documented and retained.

2228nri.717

ADMINISTRATIVE CONTROLS gggpis~ $5$ E$5&f h/7 6.5.4 NUCLEAR ASSESSMENT PROGRAM UDITS 6.

4.1 Audits of unit activities shaLL be erformed by the Nuclear Asse ment Department.

These audits shall enc pass:

a.

The conformance of unit operation to pro isions contained within the Technical Specifications and applicable La ense conditions, at least o ce per 12 months; b.

The raining, qual ifications, and performance a group, of the entir unit staff, at least once per 12 months',

c.

The resul s of actions taken to correct deficiencie occurring in unit equip nt, structures,

systems, or method of ope ation that affect nucle r safety, at least once per 6 months',

d.

The performance f activities required by the OperationaL uality

~Assurance Program to meet the criteria of Appendix B, 10 CF Part 50, at Least ce per 24 months; e ~

The fire protection pr ramnatic controls including the implemen ng procedures, at least on per. 24 months, by qualified licensee QA personneL; f.

The Radiological Environment Monitoring Program and the results thereof, at least once per 12 nths; g ~

The OFFSITE DOSE CALCULATION MANU and implementing procedures, at least once per 24 months; The PROCESS CONTROL. PROCRAM and implem ting procedures for processing and packaging of radioactive

astes, at least once per 24 months; performance of activities required by the Quality Assurance Pro ram for effluent and environmental monitor~

gg at least once per 12 mo ths',

j.

The Emer ency Plan and implementing procedures, at 1 ast once per 12 months k.

The Security an and implementing procedures, at least o ce per 12 months',

and L.

Any other area of it operation considered appropriate by the NucLear Assessment D

artment or the Vice President - Harris Nu ear Project.

6.5.4.2 Personnel performing the q ality assurance audits shall have access to the pLant operating records.

SHEARON HARRIS - UNIT 1

6-14 Amendment No.

XNSERT TO PAGE 6-14.

6.5.4 Nuclear Assessment Section Assessment Program 6.5.4.1 Assessments of facility activities shall be performed by the Nuclear Assessment Section.

Assessments willbe performance based and willbe scheduled based on plant performance and importance to safety but at a frequency not to exceed 24 months.

These assessments shall encompass:

The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions.

b.

The performance, training and qualific'ations of the entire facility staff.

c.

The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety.

The performance of activities required by the QA Program to meet the criteria of Appendix 3, 10 CFR 50.

Any other area of facility operation considered appropriate by the Vice President - Hams Nuclear Plant.

f.

The Radiological Environmental Monitoring Program and the results thereof.

g.

The OFF-SITE DOSE CALCULATIONMANUALand implementing procedures.

6.5.4.2 h.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactiv te

-pate, l0of Assessments of activities prescribed by the o e of Federal Regulations will be performed at the frequencies prescribed by the applicable regulation.

These

~

assessments shall encompass:

a.

Emergency Preparedness (per 10 CFR 50.54(t))

b.

Security (per 10 CFR 50.54(p))

gackia8oo ProleaÃon (pe<

io erg. zo. >ioi (c>)

2228nri.717

INSERT TO PAGE 6-14 (CONTINUED).

6.5.4.3 The NAS shall include at least three individuals to perform the Independent Safety Engineering Group (ISEG) function. Each reviewer shall have a bachelor's degree in engineering or related science or equivalent and at least two years professional level experience in his field, at least one year of which shall be in the nuclear field.

6.5.4.3.1 The NAS shall function to examine unit operating characteristics, NRC issuances.

industry advisories, Licensee Event Reports, and other sources of unit design information which may indicate areas of improving'nit safety.

~ Review responsibilities shall also include plant operations, modifications, maintenance, and surveillances to verify independently that these activities are performed safely and correctly and that human errors are reduced as much as practical.

222 Snri.717

ADMINISTRATIVE CONTROLS coRos g~~/<<r.~&A 0 > < (ggyehc.o )

6.5.4 Records of audits shall be pre red and retained.

6.5.4.4 udit reports encompassed by Speci 'cation 6.5.4.1 shall be

prepared, a

roved by the Manager - Nuclear Ass sment Department, and forwarded, wit in 30 days after completion of the udit, to the Executive Vice President - Powe

Supply, Senior Vice President " Nu ear Generation, Vice President Harris uclear Project, PLant General Mana r, and the management positions responsible for the areas audited.

AUTHORITY 6.5.4.5 The Manager - Nuclea Assessment Department shall be resp sible for e following:

a.

Administering the Nuclear A

essment Department Audit Program.

b.

Approval of the individuals sele ted to conduct quality assurance udits

~

6.5.4.6 Au personnel shall be independent o

he area audited.

6.5.4.7 Selects n of personnel for auditing assignme ts shall be based on experience or trai 'ng that establishes that their quali 'cations are comnen" surate with the comp xity or special nature of the activi 'es to be audited.

In selecting audit per nnel, consideration shall be given to pecial abilities, specialized t hnical training, prior pertinent expe

'ence, personal characteristics, d education.

6.5.4.8 Qualified outside co

ultants, or other individuals independ t from those personneL directLy involve in plant operation, shall be used to au ment the audit teams when necessary.

6.5.5 OUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM 6.5.5.1 An independent fire protection and loss prevention inspection and audit shall be performed at Least once per 12 months using either qualified offsite licensee personnel or an outside fire protection firm.

6.5.5.2 An inspection and audit of the fire protection and Loss prevention program shall be performed by an outside qualified fire consultant at inter" vals no greater than 36 months.

6.5.5.3 Copies of the audit reports and responses to them shall, be forwarded to the Vice President " Harris Nuclear Ra&~ and the Manager - Nuclear Assessment ~eeeaeae.

P/n'nV Vcc~l>4 6 ~ 6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

SHEARON HARRIS - UNIT 1

6-15 Amendment No.

ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION (Conti.ued) a.

The Coamission shall be nocified and a report submicted pursuant to the requirements of Sectiqn 50.73 to 10 CFR Pare 50, and b.

Each REPORTABLE EVENT shall be reviewed by. che

PNSC, and che results of this review shall be submitted to the Manager - Huclear i~~.

SecTi ow Pt c4 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions sha1.L be taken in the event a Safecy Limit is.

viol.aced:

a ~

b.

The NRC Operations Center shall be nocif ied by telephone as soon as possibLe and in all. cases wichin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

The Vice Presidenc-Harris.Nuclear

~~eve sh be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; F'LauT A Safety Limic Violation Reporc sha1,1 be prepared.

The report shall be reviewed by che PNSC.

This report shall describe:

(1) applibable circumstances preceding the violation, (2) effects of the violation upon facility components,

systems, or structures, and (3) corrective action taken to prevent recurrence; C ~

The Safety Limit Violation Report shall be submicted, within 14 days of the vioLation, to che Commission, the Manager - Nuclear Assessment i4q~~m, and the Vice President - Harris Nuclear

~joe+;

and

+~<+ioH PlavC Operacion of che unic shalL noc be resumed until authorized by the Cori s sion.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shaLL be established, implemented; and maintained covering the activities referenced below:

a ~

The applicable procedures recoamended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; b.

The emergency operating pracedures required co implemenc the requirements of HUREG-0737 and Supplement 1 to NUREG"0737 as stated in Generic Letter No. 82-33; C ~

d.

Securicy Plan implemencacion',

Emergency Plan implementation; PROCESS CONTROL PROGRAM implementation; OFFSITE DOSE CALCULATIOH MANUAL implemencatian; SHEARON HARRIS - UNIT 1

6-16 Amendment, Ho.

26

ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued) h.

Records of annual physical inventory oE all sealed source material of record.

6-10.3 The foLlowing records shaLL be detained for the duration oE the unit Operating License:

a.

Records and dra~ing changes reflecting unit design modiEications made to systems and equipment described in the Final SaEety Analysis Report; b.

Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories'

~

d ~

Records of radiation exposure for all individuals entering radiation.

control areas; Records of gaseous and liquid radioactive material released to the environs; e.

Records of transient or operational cycles Eor those unit components identifi'ed in Table 5.7-1; E.

Records of reactor tests and experiments; go Records of training and qualification Eor current members of the unit staff; h.

Records of inservice inspections performed pursuant to. these Technical Specifications; 1 ~

Records of quality assurance activities required by the Corporate Quality Assurance Program; J ~

Records of reviews performed for changes made to procedures or'quipment or reviews of tests and experiments pursuant to 10 CFR 50'9',

k.

Records of meetings of the PNSC 1 ~

Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records>

Records of secondary water sampling and water qualityl n.

Records of analyues required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at, a later A~a.

This should include procedures

~fata.

SHEARON HARRIS - UNIT 1

6-25 Amendment No.

C p

AOMIHISi nATIYE CONTROLS REC":RO R~ic TIOH (Continued)

'effective at specified times and gA record showing that these procedures were followed; and Records of facility radiatian and contamination surveys.

P.

Rac.ord'

'luJa~deuV P.e.vie~

6.1" RAOIATIQN PROTECTION PROGRAM 6.LL1 Procedures for personnel radiation pratec ion shall ba prepared consistent with the requirements of 10 CFR Part 20 and shall ha approved, maintained, and adhered to far al.l operations involving personnel radfatian exposure.

I 6.12 HIGH RAOIATTON AREA 6-12.1 Pursuant ta Paragraph 20.203(c)(5} af 10 CFR Part 20, fn lieu of the "control device" ar 'alarm signal" required by Paragraph 20.203(c),

each hfgn radiaticn area, as daffnad fn 10 CFR part 20,,in which the intensity cf radfa-tion. <s equal ta or lass than 1000 mph at 45 cm (IB in. ) fram the radiaticn source or fram any surface which the radfatian penetrates shall he barricaded and conspicuously pasted as a high radiation area and entrance thereto shall he controlled hy requiring issuance af a Radiatian Mark Permit (Qfp).

Individuals qualified in radiation pratection procedures (e.g., Health Physics Technicians) cr pirsanna1 continuously escorted by such individuals may bo exemat from the RN'ssuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal ta ar lass than 1000 mph, pra vidad they are atharwisa following plant radfaticn pratec ian procedures for entry into such high radfatfan areas.

Any individual or group cf fndfviduals permitted ta enter su& areas shall ba provided with or ac="mpanied hy one or more of tha following.

A radfatfan monitoring davfca that cantinuausly indicates the radf atf on dasa rata fn the area; or A radiaticn manitoring device that contfnuausly integrates the radiation daso rata in the area and alarms when a preset integrated dcsa is receivad.

Entry into such areas with this monitoring device may ha made aftar the dose rata levels in tha area have been estab-lished and pars'annal have been made knowledgeable of them; or c.

An fndfvfdual qualfffad fn radiation protection.procedures, wit'i a radfatfon dasa rata manftcrfng davica, who is responsible far.-pro-viding pasftfvo cant?al over the actfvft'fas within the area and w"a sha11 perform periadf c radfatf on surveillance at the frequency specified by the Radiation Control Supervisor in the RWP.

6.12.2 In addUfon to the requirements of Spaciffcation 6.12.1, accessible areas with radfatf on levels greatar than 1000 mR/h at 45 cm (18 fn.) fram the radfMicn source or fram any surfacl which the radfaticn penatratas, shall ha provided with lochaf doors to prevent unauthorized

entry, and the kys ba maintained undar the administrative cantral of the shift Foreman cn <<%

SHEARQN HARRIS - UNIT 1

'L INDEX

6. 0 ADMINISTRATIVE CONTROLS SECTION PAGE

6. 1 RESPONSIBILITY.................................--.........

6-1 6.2 ORGANIZATION...............

6-1 6..2.1 ONSITE AND OFFSITE...........................

6-1 6.2.2 UNIT STAFF............................

6-1 FIGURE 6.2-1 DELETED.....................................

6-3 FIGURE 6.2-2 DELETED...................

6-4 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION.......................

6-5

.2.3 DELETED...................................................

6 6-6 6.2.4 SHIFT TECHNICAL ADVISOR..................

6-6

.3 DELETED......................

~....

~...

~ :.

~

~ ~

~

~ ~

~

~ ~

~

~ ~ ~

~

~ ~

~

6.

6-6

.4 TRAINING.....................................................

6.

6-7 6.5 REVIEW AND AUDIT................................-....

6-7 6.5.1 SAFETY AND TECHNICAL REVIEWS General Program Control..............................

6-7 Technical Evaluations.......................................

6-7 qualified Safety Reviewers..........................

~ ~

~

6-7 Safety Evaluations and Approvals............................

6-8 6.5.2 PLANT NUCLEAR SAFETY COMMITTEE (PNSC)

F

\\

unct 1 Oll o

~

~ ~ ~

~

~ ~

~

~ ~

~

~ ~ ~

~

~ ~ ~

~

~ ~

~

~ ~

~

~ ~

~

6-9 COmPOS1 tlOn ~

~

~ ~

~

~ ~

~

~ ~

~

~ ~ ~ ~ ~

6-9 Meeting Frequency..........................

6-9 uorum..................................................

6-9 Responsibilities....

6-9 ecords..........

R 6-11 SHEARON HARRIS - UNIT 1 XV111 Amendment No.

ADMINISTRATIVE CONTROLS SECTION INDEX PAGE 6.5.3 NUCLEAR ASSESSMENT SECTION INDEPENDENT REVIEW PROGRAM Function..

0rganization........

~

Review.........

ecords............................

R 6.5.4 NUCLEAR ASSESSMENT SECTION ASSESSHENT PROGRAM..............

6-11 6-11 6-12 6-13 6-13 6,5.5 OUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM....

6-14 6.6 REPORTABLE EVENT ACTION................;.

~...................

6.7 SAFETY LIMITVIOLATION............

6.8 PROCEDURES AND PROGRAMS 6.9 REPORTING RE UIREMENTS 6.9.1 ROUTINE REPORTS Startup Report Annual Reports Annual Radiological Environmental Operating Report..........

Semiannual Radioactive Effluent Release Report..............

Monthly Operating Reports Core Operating Limits Report................................

6.9.2 SPECIAL REPORTS.............

6.10 RECORD RETENTION......................

~...........

~...

~

6-16 6-16 6-20 6-20 6-20 6-21 6-22 6-23 6-24 6-24 6-24 6.11 RADIATION PROTECTION PROGRAM...

6-26 6.12 HIGH RADIATION AREA....................

6-26 6.13 PROCESS CONTROL PROGRAM PCP........................

6-27 SHEARON HARRIS

- UNIT 1 Xix Amendment No.

ADMINISTRATIVE CONTROLS 6.2.3 DELETED 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4. 1 The Shift Technical Advisor shall provide advisory technical support to the Shift Foreman in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.

The Shift Technical Advisor shall have a baccalaureate degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.

6.3 Deleted SHEARON HARRIS - UNIT I 6-6 Amendment No.

ADHINI STRATI VE CONTROLS ualified Safet Reviewers Continued These individuals shall have a baccalaureate degree in an engineering or related field or equivalent, and 2 years of related experience.

Such designation shall include the disciplines or procedure categories for which each individual is qualified.

gualified individuals or groups not on the plant staff may be relied upon to perform safety reviews if so designated by the Plant General Hanager.

6.5. 1.4 Safet Evaluations and A

rovals 6.5.1.4.

1 The safety evaluation prepared in accordance with Specification 6.5.1. 1. 1 shall include a written determination, with basis, of whether or not the procedures or changes

thereto, proposed tests and experiments and changes

thereto, and modifications constitute an unreviewed safety question as defined in Paragraph 50.59 of 10 CFR Part 50, or whether they involve a change to the Final Safety Analysis Report, the Technical Specifications, or the Operating License.

6.5. 1.4.2 The safety evaluation shall be prepared by a qualified individual.

The safety evaluation shall be reviewed by a second qualified individual.

6.5. 1.4.3 A safety evaluation and subsequent review that conclude that the subject action may involve an unreviewed safety question, a change to the Technical Specifications, or a change to the Operating License, will be referred to the Plant Nuclear Safety Committee (PNSC) for their review in accordance with Specification 6.5.2.6.

If the PNSC recommendation is that an item is an unreviewed safety question, a change to the Technical Specifications, or a change to the Operating License, the action will be referred to the Commission for approval prior to implementation.

Implementation may not proceed until after review by the Nuclear Assessment Section (NAS) in accordance with Specification 6.5.3.9.

I 6.5. 1.4.4 If a safety evaluation and subsequent review conclude that the subject action does not involve an unreviewed safety question, a change to the Technical Specification, or a change to the Operating

License, the action may be approved by the Plant General Hanager or his designee or, as applicable, by the Hanager of the primary functional area affected by the action.

The individual approving the action shall assure that the reviewers collectively possess the background and qualification in all of the disciplines necessary and important to the specific review for both safety and technical aspects.

6.5.1.4.5 A safety evaluation and subsequent review that conclude that the modifications, procedures, tests or experiments which constitute a change to the facility as described in the Final Safety Analysis Report shall be referred to the Nuclear Assessment Section for review in accordance with Specification 6.5.3.9, but implementation may proceed prior to the completion of that review.

6.5.1.4.6 The individual approving the procedure,

tests, or experiment or change thereto shall be other than those who prepared the safety evaluation or performed the safety review.

SHEARON HARRIS - UNIT I 6-8 Amendment No.

ADMINISTRATIVE CONTROLS RESPONSIBILITIES Continued b.

C.

d.

e.

h.

k.

Review of all proposed tests and experiments that affect nuclear safety and that have been initially determined to appear to constitute an unreviewed safety question, or involve an unreviewed change to the Technical Specifications; Review of all proposed changes to Appendix "A" Technical Specifications; Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety and that have been initially determined to appear to constitute an unreviewed safety question as defined in 10 CFR 50.59 or involve a change

.to the Technical Specifications; Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the Vice President

- Harris Nuclear Plant; Review of all REPORTABLE EVENTS; Review of unit operations to detect potential hazards to nuclear safety; Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant General Hanager or the Hanager

- Nuclear Assessment Section; I

Review of the Security Plan; Review of the Emergency Plan; Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President

- Harris Nuclear Plant; Review, prior to implementation, of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, the Radwaste Treatment

Systems, and the Technical Specification Equipment List Program.

6.5.2.7 The PNSC shall:

a ~

Render determinations in writing with regard to whether or not each item considered under Specification 6.5.2.6a.

through e.

constitutes an unreviewed safety question; and SHEARON HARRIS - UNIT I 6-10 Amendment No.

ADMINISTRATIVE CONTROLS RESPONSIBILITIES Continued RECORDS Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President

- Harris Nuclear Plant of disagreement between the PNSC and the Plant General Manager.

However, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6. 1. 1.

6.5.2.8 The PNSC shall maintain written minutes of each PNSC meeting that, at a minimum, document the results of all PNSC activities performed under the responsibility provisions of these Technical Specifications.

Copies shall be provided to the Vice President

- Harris Nuclear Plant and the Manager-Nuclear Assessment Section.

6.5.3 NUCLEAR ASSESSMENT SECTION INDEPENDENT REVIEW PROGRAM FUNCTION 6.5.3. 1 The Nuclear Assessment Section shall'unction to provide independent f

.review of pla'nt changes,

tests, and procedures; verify that REPORTABLE EVENTS are investigated in a timely manner and corrected in a manner that reduces the probability of recurrence of such events; and detect trends that may not be apparent to a day-to-day observer.

ORGANIZATION 6.5.3.2 The individuals assigned responsibility for independent reviews shall be technically qualified in a specified technical discipline or disciplines.

These individuals shall collectively have the experience and competence required to review activities in the following areas:

b.

C.

d.

e.f.

g.

h.

1

~

k.l.

Nuclear power plant operations, Nuclear engineering, Chemistry and radiochemistry, Metallurgy, Nondestructive testing, Instrumentation and control, Radiological safety, Mechanical and electrical engineering, Administrative controls, Seismic and environmental, guality assurance practices, and Other appropriate fields.

SHEARON HARRIS - UNIT 1 6-11 Amendment No.

ADHINISTRATIVE CONTROLS ORGANIZATION Continued 6.5.3.3 The Hanager

- Nuclear Assessment Section shall have a bachelor degree

(

in an engineering or related field and, in addition. shall have a minimum of 10 years related experience, of which a minimum of 5 years shall be in the operation and/or design of nuclear power plants.

6.5.3.4 The individuals performing independent safety reviews shall have a

bachelor degree in an engineering or related field or equivalent and, in addition, shall have a msnimum of 5 years'elated experience.

6.5.3.5 An individual may possess competence in more than one specialty area.

If sufficient expertise is not available within the Nuclear Assessment

Section, competent individuals from other Carolina Power

& Light Company organizations or outside consultants shall be utilized in performing independent reviews and investigations.

6.5.3.6 The documents submitted under 6.5.3.9 shall be reviewed by individuals meeting the requirements of 6.5.3.2 and 6.5.3.4 to ensure disciplines are encompassed.

Hultiple reviews will be conducted on documents where required to meet applicable disciplines of 6.5.3.2.

6.5.3.7 Independent safety reviews shall be performed by individuals not directly involved with the activity under review or responsible for the activity under review.

6.5.3.8 The Nuclear Assessment Section independent safety review program shall be conducted in accordance with written, approved procedures.

REVIEW 6.5.3.9 The Nuclear Assessment Section shall perform reviews of the following:

a.

b.

C.

d.

Written safety evaluations of changes in the facility as described in the Safety Analysis Report, changes in procedures as described in the Safety Analysis Report, and tests or experiments not described in the Safety Analysis Report which are completed without prior NRC approval under the provisions of 10CFR50.59(a)(1).

These reviews are to verify that such chances,

tests, or experiments do not involve a change in the Technical Specifications or an unreviewed safety question as defined in 10CFR50.59(a)(2).

These reviews may be conducted after appropriate management

approval, and implementation may proceed prior to completion of the review.

Proposed changes in procedures reguired by these Technical Specifications, proposed changes 1n the facility, or proposed tests or experiments, any of which involve a change in the Technical Specifications or an unreviewed safety question pursuant to 10CFR50.59(a)(2) prior to implementation.

Proposed changes to the Technical Specifications or this Operating License prior to implementation.

Violations, deviations and REPORTABLE EVENTS, which require reporting to the NRC in writing, such as:

SHEARON HARRIS

- UNIT 1 6-12 Amendment No.

ADHINISTRATIVE CONTROLS REVIEW Continued 1)

Violations of applicable

codes, regulations,

orders, Technical Specifications.

license requirements or internal procedures or instructions having safety significance, 2)

Significant operating abnormalities or deviations from normal or expected performance of plant safety-related structures,

systems, or components, and 3)

REPORTABLE EVENTS, as specified in 10CFR50.73.

e.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures,

systems, or components that could affect nuclear safety.

RECORDS Any other matter involving safe operation of the nuclear power plant that the Manager

- Nuclear Assessment

Section, deems appropriate for consideration or which is referred to the Hanager-Nuclear Assessment

Section, by the on-site operating organization, Plant Nuclear Safety Committee (PNSC) or by other functional organizational units within Carolina Power 8 Light Company.

6.5.3.10 Results of Nuclear Assessment Section independent safety reviews shall be documented and retained.

6.5.4 NUCLEAR ASSESSMENT SECTION ASSESSMENT PROGRAM 6.5.4.1 Assessments of facility activities shall be performed by the Nuclear Assessment Section.

Assessments will be performance based and will be scheduled based on plant performance and importance to safety but at a frequency not to exceed 24 months.

These assessments shall encompass:

a.

The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions.

b.

The performance, training and qualifications of the entire facility staff.

c.

The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety.

d.

The performance of activities required by the OA Program to meet the criteria of Appendix B.

10 CFR Part 50.

e.

"Any other area of'acility operation considered appropriate

'y the Vice President

- Harris Nuclear Plant, f.

The Radiological Environmental Monitoring Program and the results thereof.

g.

The OFF-SITE DOSE CALCULATION HANUAL and implementing procedures.

SHEARON HARRIS

- UNIT 1

, 6-13 Amendment No.

ADMINISTRATIVECONTROLS 6.5.4 NUCLEAR ASSESSMENT SECTION ASSESSMENT PROGRAM (Continued) 6.5.4.2 6.5.4.3 h.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes.

Assessments of activities prescribed by Title 10 of the Code of Federal Regulations will be performed at the frequencies prescribed by the applicable regulation.

These assessments shall encompass:

a.

Emergency Preparedness (per 10 CFR 50.54(t))

b.

Security (per 10 CFR 50.54(p))

c.

Radiation Protection (per 10 CFR 20.1101(c))

The NAS shall include at least three individuals to perform the Independent Safety Engineering Group (ISEG) function.

Each reviewer shali have a bachelor's degree in engineering or related science or equivalent and at least two years professional level experience in his field, at least one year of which shall be in the nuclear field.

6.5.4.3.1 The NAS shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design information which may indicate areas of improving unit safety.

Review responsibilities shall also include plant operations, modifications, maintenance, and surveillances to verify independently that these activities are performed safely and correctly and that human errors are reduced as much as practical.

6.5.5 OUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM 6.5.5.1 An independent fire protection and lohs prevention inspection and audit shall be performed at least once per 12 months using either qualified offsite licensee personnel or an outside fire protection firm.

6.5.5.2 An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 36 months.

6.5.5.3 Copies of the audit reports and responses to them shall be forwarded to the Vice President

- Harris Nuclear Plant and the Manager-Nuclear Assessment Section.

(PAGE 6-15 DELETED)

(NEXT PAGE IS 6-16)

SHEARON HARRIS

- UNIT 1 6-14 Amendment No.

ADMINISTRATIVECONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a

~

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

PNSC, and the results of this review shall be submitted to the Manager

- Nuclear Assessment Section and the Vice President

- Harris Nuclear Plant.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

The Vice President-Harris Nuclear Plant shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; b.

C.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PNSC.

This report shall describe:

(1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components,

systems, or structures.

and (3) corrective action taken to prevent recurrence; The Safety Limit Violation Report shall be submitted, within 14 days of the violation, to the Commission, the Manager

- Nuclear Assessment

Section, and the Vice President

- Harris Nuclear Plant; I

and d.

Operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a

~

b.

C.

d.

e.

The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978; The emergency operating procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Generic Letter No. 82-33; Security Plan implementation; Emergency Plan implementation; PROCESS CONTROL PROGRAM implementation; OFFSITE DOSE CALCULATION MANUAL implementation; SHEARON HARRIS - UNIT 1 6-16 Amendment No.

ADHINISTRATIVE CONTROLS RECORD RETENTION Continued h.

Records of annual physical inventory of all sealed source material of record.

6.10.3 The following records shall be retained for the duration of the unit Operating License:

b.

C.

d.

e.

9.

h.

k.

n.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report; Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories; Records of radiation exposure for all individuals entering radiation control areas; Records of gaseous and liquid radioactive material released to the environs; Records of transient or operational cycles for those unit components identified in Table 5.7-1; Records of reactor tests and experiments; Records of training and qualification for current members of the unit staff.

Records of inseryice inspections performed pursuant to these Technical Specifications; Records of quality assur ance activities required by the Corporate guality Assurance Program; Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59; Records of'eetings of the PNSC; Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records; Records of secondary water sampling and water quality; Records of analyses required by the Radiological Envir'onmental Honitoring Program that would permit evaluation of the accuracy of the analysis at a later date.

This should include procedures SHEARON HARRIS

- UNIT 1 6-25 Amendment No.

ADMINISTRATIVE CONTROLS RECORD RETENTION Continued effective at specified times and gA records showing that these procedures were followed; and o.

Records of facility radiation and contamination surveys.

p.

Records of independent reviews.

6.11 RADIATION PROTECTION PROGRAM 6.11. 1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adher ed to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 Pursuant to Paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the "control device" or "alarm signal" required by Paragraph 20.203(c),

each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).

Individuals qualified in radiation protection procedures (e.g.,

Health Physics Technicians or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device that continuously indicates the radiation dose rate in the area; or b.

c ~

A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received..

Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or An individual qualified in radiation protection procedures, with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and who shall perform periodic radiation surveillance at the frequency specified by the Radiation Control Supervisor in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, accessible

.areas with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the

. radiation source or from any surface which the radiation penetrates, shall be rovided with locked doors to prevent unauthorized

entry, and the keys shall e maintained under the administrative control of the shift Foreman on duty SHEARON HARRIS - UNIT 1

6-26 Amendment No.

0

~

<<\\

4 p

Form No.: NG-502 10/90 Attachment 4

to NGGM 304-01 OUTGOING CORRESPONDENCE S

CHANG DE F

C 0

0 JUL lv>1 ggy 3 ASSOCIATED DOCUMENT IDENTIFICATION:

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LETTER NUMBER, TITLE, DOCUMENT NUMBER) gr c/- o<wowe<

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~5~ g~~Ww 7-r Ao~~~ 5'uter, NOTES:

(1) If noted FSAR changes have already been identified and are being processed per another process or procedure (e.g.,

NPMP, CAP),

a note to that effect is sufficient.

(2) If a complete FSAR change package is not currently available,

'insert the responsible person's name, anticipated completion date, and the method being utilized for tracking (e.g., FACTS'.

(3) Refer to 10CFR50.71 and applicable nuclear pro]ect FSAR Change Control procedure(s) if in doubt of applicable change requirements.

(1) FSAR PAGE(S)/FIGURE(S)

AFFECTED:

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DEC / E (I/~PuT /m< g&~. C-ui&W // YQ - $<Z, gW~/vow 7 o VCR' (o Af JA-a QEcr foN /7.3 (2) DESCRIPTION OF CHANGE (See Notes):

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PREPARER:

DATE:

(3041ATTS)

ML18011A821

Text

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