Text

Proposed Tech Specs Allowing Implementation of Functional Role & Responsibilities of Nuclear Assessment Dept
	ML18011A173
Person / Time
Site:	Harris
Issue date:	09/15/1993
From:	; CAROLINA POWER & LIGHT CO.
To:	;
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ML18011A172	List: ML18011A170; ML18011A173;
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	NUDOCS 9309200106
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ENCLOSURE 4 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/OPERATING LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT NUCLEAR ASSESSMENT DEPARTMENT FUNCTIONAL CHANGES REVISED TECHNICAL SPECIFICATION PAGES PAGE CHANGE INSTRUCTIONS REMOVED PAGE INSERTED PAGE XVi1.l.

xviii Xix Xix 6-6 6-6 6-8 6-8 6-9 6-9 6-11 6-11 6-12 6-13 6-14 6-12 6-13 6-14 6-15 6-16 6-25 6-26 6-16 6-25 6-26

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<2039Gt.U)

ENCLOSURE 5

SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/OPERATING LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT NUCLEAR ASSESSMENT DEPARTMENT FUNCTIONAL CHANGES REVISED TECHNICAL SPECIFICATION PAGES (2039GLU)

e INOEX

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............. -... ~.... -........ ""

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

6"4 6-5 6.2.3 DELETE

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6. 2.4 SHIFT TECHNICAL ADVISOR.....................

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

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

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

Technical Evaluations.....................................

6-7 6-7 gualified Safety Reviewers........................

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

6.5.2 PLANT NUCLEAR SAFETY COMMITTEE (PNSC) 6-8 Function.............

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omposstlon..............................

Meeting Frequency.

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6-9 6"9 6-9 6-9 Records...

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6-11 SHEARON HARRIS - UNIT 3.

Xviii Amendment No. ~

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INDEX ADMINISTRATIVE CONTROLS SECTION PACE pfuCLEAk ASSESSM &7I&AXTNEiV77NDEPEtuuENr /EV'N/ PRuGRAH 6 ~ 5 ~ 3 Funct ion ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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Records

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6"11 6-12 6-13 NllC'L Ag AsM$Sht &I7 DCPARvNEjV 6.5.4 AssEssAt &rI pgasgAM 4-J3 Auex+6 C?E9V1

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RCCQTdSe

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6.5.5

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DCM~

6.6 REPORTABLE EVENT ACTIONo ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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6.7 SAFETY LIMIT VIOLATIONo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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6.8 PROCEDURES AND PROGRAMS'~

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. REPORTINC RE UZREMENTS 6.9 '

ROUTINE REPORTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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6-16 6"20 Startup Report.

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6-20 Annual.

Reports

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AnnuaL RadioLogical Environmental Operating Report.... ~.....

Semiannual.

Radioactive Effluent Release Report.

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Monthly Operat1ng Reports.

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6 10 RECORD RETENTIONe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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6-26 6.13 PROCESS CONTROL PROGRAM (PCP)

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

ADMINISTRATIVE CONTROLS

. 3 PROJECT ASSESSMENT 'PA)

SECTION FUNCT 6.2.3.1 Th PA Section shall function to examine unit operating characteristi NRC issuances, industry advisories (including information forwarded by IN from their evaluation of all industry LERs),

and other sources of unit de 'gn and operating experience information; including units of similar design, wh'ch may indicate areas for improving unit safety.

The PA Section shall eke deta ed recommendations for revised procedures, equipment modifications, maintenance ctivities, operations activities, or other means of improving unit safety, to ppropriate levels of management, up to and including the Executive Vice P

sident - Power Supply, if necessary.

COMPOSITION 6.2.3.2 The PA Section shall include at east five, dedicated, full-time engineers located on site.

Each shall have baccalaureate degree in engineering or related science and at least 2

ars professional level experience in his field, at least 1 year of whic experience shall be in the nuclear field.

RESPONSIBILITIES 6.2.3.3 The PA Section shall be responsible for maintaining urveillance of unit activities to provide independent verification that these ctivities are performed correctly and that human errors are reduced as much as actical

~

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

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 scien-tific 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 ot respo s

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SHEARON HARRIS UNIT 1

6"6 Amendment No.

26

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4

ADMINISTRATIVE 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.

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 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 Department in accordance with Specification 6.5.3.9.

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 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 the specific review for both safety and technical aspects.

to than ~< $ c f'f ~ J~c.<<~Kg 6.5.1.4.5 A safety evaluation arfd subsequent review that conclude that the subject action involves a change/in the Final Safety Analysis Report shall be referred to the Nuclear Assessment Department 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 1

6-8 Amendment No.

ADMINISTRATIVE CONTROLS 6.5.2 PLANT NUCLEAR SAFETY COMMITTEE (PNSC)

FUNCTION 6.5.2.1 The PNSC shall function to advise the Plant General Hanager on all matters related to nuclear safety.

COMPOSITION 6.5.2.2 The PNSC shall be composed of the:

Chairman'.

Hember:

Member:

Member.'ember.'ember.'lant General Manager Manager - Operations Manager Technical Support Manager Maintenance Manager - Environmental and Radiation Control Manager - Plant Programs and Procedures Manager - Regulator Com liance Hana er A

C-Harris Pl n 6.5.2.3 The Chairman may designate in writing other regular members who may serve as Acting Chairman of PNSC meetings.

All alternate members shall be appointed in writing by the PNSC Chairman.

Alternates shall be designated for specific regular PNSC members and.shall have expertise in the same general area as the regular member they represent.

No more than two alternates shall participate as voting members in PNSC activities at any one time.

HEETING FRE UENCY 6.5.2.4 The PNSC shall meet at least once per calendar month and as convened by the PNSC Chairman or his designated alternate.

The PNSC must meet in session to perform its function under these Technical Specifications.

QUORUM 6.5.2.5 The quorum of the PNSC necessary for the performance of the PNSC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.2.6 The PNSC shall be responsible for:

a.

Review of proposed procedures or changes thereto that have been initially determined to constitute an unreviewed safety question or involve an unreviewed change to the Technical SpecificationsR SHEARON HARRIS - UNIT 1

6-9 Amendment No. 26

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Cont inued) provxde written notxfxcatzon wathxn 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Voce President Harris Nuclear Project and the Manager - Nuclear Assessment Department of disagreement between the PHSC and the Plant General Manager.

However, the Plant General Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS The PHSC shall maintain written minutes of each PNSC meeting th<<

at a minimum, document the results of all PHSC activities performed "nder the responsibility provisions of these Technical, Specifications.

Copies shall be provided to the Vice President - Harris Nuclear Project and the Manager-Hpclear Assessment Department.

6.5'.3 NUCLEAR ASSESSMEHT DEPARTMENT INDEPENDENT REVIEW PROGRAM FUNCTION 6

5 3 ~ 1 The Nuclear Assessment Department shall function to provide independent review of plant changes,

tests, and procedures,'erify 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 Eor independent reviews shall be technically qualifie'd in a specified technical discipline or disciplines.

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

a.

Nuclear power plant operations, b,

Nuclear engineering, c.

Chemistry and radiochemistry, d.

Metallurgy,

g. 4 Instrumentation and control, g Radiological safety, h Mechanical and electrical engineering,

< Administrative control~a k Quality assurance practices, o Nondestroctive testing,~an LOther appropriate fields SHEARON HARRIS - UNIT 1

6-11 Amendment No 26

ADMINISTRATIVE CONTROLS ORGANIZATION (Cont inued)

I Salty Revue& Quit 4a c4Lor 6.5.3.3 The Manager Nuclear shall have a

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.

6.5.3.4 The independent safety review program reviewers shall each have a

bacLOLor-degree in an engineering or related field or equivalent and, in addition, shall have a minimum 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 Department, competent individuals from other Carolina Power

& Light Company organizations or outside consultants shall be utilized in performing independent reviews and investigations'.5.3.6 At least three individual.s, qualified as discussed in Specifica-tion 6.5.3.2 above shall review each item submitted under the requirements of S ecification 6.5.3.9.

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 Department independent safety review program shall be conducted in accordance with written, approved procedures

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REVIEW

.3.9 The Nuclear Assessment Department shall perform reviews of'he fol ing.

a.

'tten safety evaluations for all procedures and programs e'equired by cification 6.8 and other procedures that affect nuclear safety and cha s thereto, and proposed tests or experiments and proposed modificatio any of which constitute a change to the Final Safety Analysis Repor Implementation may proceed prior to completion of the review,'

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All procedures and progra required by Specification 6.8 and other procedures that affect nuclea safety and changes thereto that con-stitute an unreviewed safety que ion as defined in Paragraph 50.59 of 10 CFR Part 50 or involve a chang to the Technical Specifications; co All proposed tests or experiments that constit an unreviewed safety question as defined in Paragraph 50.59 of CFR Part 50 or involve a change to the Technical Specifications prio o implemen-tation; de All proposed changes to the Technical Specifications and Operate License',

SHEARON HARRIS - UNIT 1

6-12 Amendment No.

2Q

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.

(2039GLU)

ADMINISTRATIVE CONTROLS EVIEM (Cont inued) e.

Violations, which require written notification to the Commission, of applicable

codes, regulations,

orders, Technical Specifications, license requirements, internal procedures or instructions having nuclear safety significance, significant operating abnormalities or deviations from normal and expected performance of plant safety-related structures,

systems, or components; f.

Al REPORTABLE EVENTS; g.

All p oposed modifications that constitute an unreviewed safety questi as defined in Paragraph 50.59 of 10 CFR Part 50 or involve a change to the Technical Specifications; h.

Any other tter involving safe operation of the nuclear power plant that the Man er Nuclear Assessment Department deems appropriate for considera on or which is referred to the Manager - Nuclear Assessment Depa tment by the onsite operating organization or other functional organ ational units within Carolina Power

& Light Company; i.

All recognized indica ions of an unanticipated deficiency in some aspect of design or op ation of structures,

systems, or components that could affect nuclea safety; and j.

Reports and minutes of the NSC.

6.5.3.10 Review of items considered un r Specification 6.5.3.9.e, h an'd j above shall include the results of any in estigations made and the recommenda-tions resulting from these investigations prevent or reduce the probability of recurrence of the event.

RECORDS 6 '.3.11 Records of Nuclear Assessment Department reviews performed under Specification 6.5.3.9, including recommendations an

concerns, shall be prepared and distributed as indicated below:

a.

Copies of documented reviews shall be retaine in the NAD files.

b.

Recommendations and concerns Manager and Vice President-of completion of the review.

encompassed by Specification General Manager and the Vice every other month.

shall be submitted the Plant General Harris Nuclear Projec within 14 days A report summarizing e reviews 6.5.3.9 shall be provide to the Plant President " Harris Nuclea Project C ~

A summation of recommendations and concerns of the Nuclear Assessment Department shall be submitted to the Chairman/Pre ident and Chief Executive Officer and other appropriate senior mana ment personnel at least eve'ry other month.

SHEARON HARRIS UNIT 1

6-13 Amendment No. 2

INSERT TO PAGES 6-12 AND 6-13.

REVIEW The Nuclear Assessment Department shall perform reviews of the following:

a o 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.

b.

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 of plant safety-related structures,

systems, or components, and 3 ~

REPORTABLE EVENTS as specified in 10 CFR 50.73, which require reporting to the NRC in writing.

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.

Any other matter involving safe operation of the nuclear power plant that the Manager Nuclear Assessment Department, deems appropriate for consideration or which is referred to the Manager Nuclear Assessment Department, by the on-site operating organization, Plant Nuclear Safety Committee (PNSC) or by other functional organizational units within CPGL.

(2039GLU)

INSERT TO PAGES 6-12 AND 6-13.

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

6.5.3.11 Potentially adverse conditions shall be submitted in accordance with the corrective action program.

6.5.3.12 A briefing of the Nuclear Assessment Department activities, along with any potential issues and recommendations shall be presented to the Executive Vice President Nuclear Generation Group on an approximately bimonthly frequency.

Copies of this presentation shall be provided to the Vice President Harris Nuclear Project, Plant General

Manager, and others as appropriate.

(2039GLU)

~

ADMINISTRATIVE CONTROLS Sskss thzQ+

6.5.4 NUCLEAR ASSESSMENT DEPARTMENT~

PROGRAM UDITS 6.5..1 Audits'of unit activities shall be performed by the Nuclear Asses ent Department.

These audits shall encompass:

a

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The conformance of unit operation to provisions contained within the echnical Specifications and applicable license conditions, at least o

e per 12 months; b.

The t aining, qualifications, and performance as a group, of the

'entire nit staff, at least once per 12 months; C ~

The resul of actions taken to correct deficiencies occurring in unit equipm t, structures,

systems, or method of operation that affect nuclea safety, at least once per 6 months; d.

The performance activities required by the Operational Quality Assurance Program o meet. the criteria of Appendix B, 10 CFR Part 50, at least o

e per 24 months; e.

The fire protection pro rammatic controls including the implementing procedures, at least onc per 24 months, by qualified licensee QA personnel; The Radiological Environmenta Monitoring Program and the results thereof, at least once per 12 m

ths; g ~

The OFFSITE DOSE CALCULATION MANUA and implementing procedures, at least once per 24 months; h.

The PROCESS CONTROL PROGRAM and impleme ing procedures for processing and packaging of radioactive w stes, at least once per 24 months; 1 ~

The performance of activities required by'the uality Assurance Program for effluent and environmental monitori

, at least once per 12 months',

J

~

The Emergency Plan and implementing procedures, at 1

st once per 12 months; k.

The Security Plan and implementing procedures, at least o

e per 12 months; and Any other area of unit operation considered appropriate by the Nuclear Assessment Department or the Vice President - Harris Nuc ear Project.

6.5.4.2 Personnel performing the quality assurance audits shall have access to the lant o eratin records.

SHEARON HARRIS - UNIT 1

6-14 Amendment No. 26

ADMINISTRATIVE CONTROLS CORDS 6.5.4.

Records of audits shall be prepared and retained.

6.5.4.4 dit reports encompassed by Specification 6.5.4.1 shal,l be

prepared, ap oved by the Manager - Nuclear Assessment Department, and forwarded, with'0 days after completion of the audit, to the Executive Vice President Power upply, Senior Vice President - Nuclear Generation, Vice President Harris clear Project, Plant General

Manager, and the management positions responsible r the areas audited.

AUTHORITY 6.5.4.5 The Manager " Nuclear the following:

sessment Department shall be responsible for a.

Administering the Nuclear Ass sment Department Audit Program.

b.

Approval of the individuals select to conduct quality assurance audits.

6.5.4.6 Audit personnel shall be independent of t area audited.

6.5.4.7 Selection of personnel for auditing assignment shall be based on experience or training that establishes that their qualifi tions are commen-surate with the complexity or special nature of the activitie to be audited.

In selecting audit personnel, consideration shall be given to s

cial abilities, specialized technical training, prior pertinent experi ce, personal characteristics, and education.

6.5.4.8 Qualified outside consultants, or other individuals independen from those personnel directly involved in plant operation, shall be used to augm t

the audit teams when necessary.

6.5.5 OUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM T'ai

~cT'ioH lACOVPcroT lQ fq g~~7i'Og )7,3,3.S o% %he.V~~~

.1 An independent fire protection and loss prevention inspection and audit s

be performed at least once per 12 months using either qualified offsite license sonnel or an outside fire protection firm.

6.5.5 '

An inspection and au the fire protection and loss prevention program shall be performed by an outs'alified fire consultant at inter-vals no greater than 36 months.

6.5.5.3 Copies of the audit reports and responses to them be forwarded to the Vice President Harris Nuclear Project and the Manager Nu Assessment Department.

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.

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INSERT TO PAGE 6-14+

6.5.4 Nuclear Assessment Department Assessment Program 6.5.4.1 Assessments of the following functions/areas will be routinely performed!

A.

B.

C.

D E.

F Operations Maintenance Engineering (Design/Modifications/Technical Support)

E&RC (Chemistry/Radiological Controls/Environmental Monitoring)

Fire Protection Nuclear Fuels I

Assessments of two functions/areas will be performed at the prescribed frequencies:

G.

H.

Emergency Preparedness (PER 10 CFR 50.54(t))

Security (PER 10 CFR 50.54(p))

6.5.4.2 As part of the overall assessment scheduling activity, the following program elements will be considered and periodically included in the scope of functional assessments.

When several assessments indicate potential problems in a program element, a

special assessment of that element will be performed.

A.

B.

C.

D ~

E.

F.

G.

HI.

J.

K.

L.

M N.

O.

P Q.

R.

Control of Measuring and Test Equipment Control of Purchased Material Equipment and Services Control of Special Processes Corrective Action Document Control Handling, Shipping, and Storage Identification and Control of Materials Parts and Components Inspection Inspection,

Test, and Operating Status (Equipment Control)

Instructions, Procedures, and Drawings Nonconforming Materials, Parts, and Components Organization Outage Management Procurement Document Control Records Test Control Training and Qualification The conformance of unit operations to provisions contained within the Technical Specifications and applicable license conditions.

6.5.4.3 The NAD Plant Assessment (PA) Section 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 surveillance to verify independently that these activities are performed safely and correctly and that human errors are reduced as much as practical.

(2039GLU)

~

6.5.4.3.1 The PA Section shall include at least three dedicated, full-time reviewers located on-site.

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

Reference:

FSAR Section 17.3.3 (2039GLU)

ADMINISTRATIVE 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 Petained for the duration of the unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report; b ~

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

c ~

Records of radiation exposure for all individuals entering radiation control areas; d ~

Records of gaseous and liquid radioactive material released to the environs',

e.

Records of transient or operational cycles for those unit components identified in Table 5.7-1; f.

Records of reactor tests and experiments; Records of training and qualification for 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; Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.593 k.

Records of meetings 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; m.

Records of secondary water sampling and water quality) n.

'Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later data.

This should include procedures SHEARON HARRIS UNIT 1

6-25 Amendment No.

~

'4

~

AOMINISi RATIVE CONTROLS RECORO RETENTION Continued)

C effective at specified times and gA'records showing that these procedures were followed; and o.

Records of. facility rqdiation and contamination surveys.

P.

Recon@ < iudePmclevT reviews ~g~<mQ by thz Auchar hssessmsA

6. 11 RAOIATION PROTECTION PROGRAM

~t'I%&I 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of M CFR part 20 and shall be approved, maintained, and adhered to for al.l operations involving personnel radiation exposure.

6.12 HIGH RAOIATION 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 radia-tion 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, pro-vided 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:

b.

c A radiation monitoring device that continuously indicates the radiation dose rate in the area; or 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 estab-lished 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 pro-viding 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 addi~ion 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 radi&ion source or from any surface which the radiation penetrates, shall be provided with. locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift Foreman on duty SHEARON HARRIS - UNIT 1, 6"26

\\

I II g e'l

INDEX

6. 0 ADMINISTRATIVE CONTROLS SECTION PAGE 6o 1 RESPONSIBILITYe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

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

6-1 6.2. 1 ONSITE AND OFFSITE..............................

~.

~

6-1

.2.2 UNIT STAFF.................................................

6 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 6.3 DELETED.

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)

Function.....

~

6-9 C

~ +

~

OmPOS 1tlOtl o

~

~ ~

~

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

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

6-9 R

~ I

~

esponslbllltles

~ ~........

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

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

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

'n i'NDEX ADMINISTRATIVE CONTROLS SECTION 6.5.3 NUCLEAR ASSESSMENT DEPARTMENT INDEPENDENT REVIEW PROGRAM PAGE FUnct 1 On ~ ~

~

6-11 rganization.....-...........................................

0 6-11 eview............................................,..........

R 6-12 ecords.....................................................

R 6-13 6.5.4 NUCLEAR ASSESSMENT DEPARTMENT ASSESSMENT PROGRAM...........

6-13

.5.5 DELETED.....................................................

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

6-16

6. 7 SAFETY LIMITVIOLATION.......................................

6-16 6.8 PROCEDURES AND PROGRAMS................

6-16

6. 9 REPORTING RE UIREMENTS 6.9. 1 ROUTINE REPORTS.............................................

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

~.

6-20 nnual Reports..............................................

A 6-20 Annual Radiological Environmental Operating Report..........

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

6-21 6-22 Monthly Operating Reports...................................

6-23 Core Operating Limits Report................................

6-24 6.9.2 SPECIAL REPORTS.............................................

6-24

6. 10 RECORD RETENTION............................................

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 X1X Amendment No.

., ADMINISTRATIVE CONT S

6.2.3 DELETED 6.2. 4 SHIFT TECHNICAL ADVISOR 6.2.4. I 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.

C

~

..ADMINISTRATIVE CONT S

uglified 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 Manager.

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 Department in accordance with Specification 6.5.3.9.

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 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 the specific review for both safety and technical aspects.

6.5. 1.4.5 A safety evaluation and subsequent review that conclude that the subject action involves a change to the facility*as described in the Final Safety Analysis Report shall be referred to the Nuclear Assessment Department 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 1

6-8 Amendment No.

~

ADMINISTRATIVE CONT S

6.5.2 PLANT NUCLEAR SAFETY COMMITTEE PNSC FUNCTION 6.5.2. 1 The PNSC shall function to advise the Plant General Manager on all matters related to nuclear safety.

COMPOS IT ION 6.5.2.2 The PNSC shall be composed of the:

Chairman:

Member:

Plant General Manager Manager - Operations Manager - Technical Support Manager

- Maintenance Manager

- Environmental and Radiation Control Manager - Plant Programs and Procedures Manager

- Regulatory Compliance 6.5.2.3 The Chairman may designate in writing other regular members who may serve as Acting Chairman of PNSC meetings.

All alternate members shall be appointed in writing by the PNSC Chairman.

Alternates shall be designated for specific regular PNSC members and shall have expertise in the same general area as the regular member they represent.

No more than two alternates shall participate as voting members in PNSC activities at any one time.

HEETING FRE UENCY 6.5.2.4 The PNSC shall meet at least once per calendar month and as convened by the PNSC Chairman or his designated alternate.

The PNSC must meet in session to perform its function under these Technical Specifications.

QUORUM 6.5.2.5 The quorum of the PNSC necessary for the performance of the PNSC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including alternates.

RESPONSIBILITIES 6.5.2.6 The PNSC shall be responsible for:

a.

Review of proposed procedures or changes thereto that have been initially determined to constitute an unreviewed safety question or involve an unreviewed change to the Technical Specifications; SHEARON HARRIS - UNIT I 6-9 Amendment No.

C r'DMINISTRATIVE CONT S

y

~

RESPONSIBILITIES Continued b.

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 Project and the Manager

- Nuclear Assessment Department 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 Project and the Manager-Nuclear Assessment Department.

6.5.3 NUCLEAR ASSESSMENT DEPARTMENT INDEPENDENT REVIEW PROGRAM FUNCTION 6.5.3. 1 The Nuclear Assessment Department shall function to provide independent review of plant 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:

a ~

b.

C.

d.

e.f.

g, h.

1

~

0 J

0 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.

tw ADHIN I STRATI VE CONT S

ORGANIZATION Continued 6.5.3.3 The Manager

- Nuclear Safety Review Unit shall have a bachelor 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.

6.5.3.4 The independent safety review program reviewers shall each have a

bachelor degree in an engineering or related field or equivalent

and, in addition, shall have a minimum 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 Department, competent individuals from other Carolina Power 8 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.

Multiple 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 Department independent safety review program shall be conducted in accordance with written, approved procedures.

REVIEW 6.5.3.9 The Nuclear Assessment Department 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)(l).

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 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 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 IOCFR50.59(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 I 6-12 Amendment No.

(y " ADMINISTRATIVE CONT e

P J

~

(

~

REVIEW Continued e.

RECORDS 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, which require reporting to the NRC in writing.

All recognized 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 of the nuclear power plant that the Manager - Nuclear Assessment Department, deems appropriate for consideration or which is referred to the Hanager-Nuclear Assessment Department, by the on-site operating organization, Plant Nuclear Safety Committee (PNSC) or by other functional organizational units within Carolina Power

& Light Company.

6.5.3.10 6.5.3.11 6.5.3.12 Results of Nuclear Assessment Department independent safety reviews shall be documented and retained.

Potentially adverse conditions shall be submitted in accordance with the corrective action program.

A briefing of the Nuclear Assessment Department activities, along with any potential issues and recommendations shall be presented to the Executive Vice President

- Nuclear Generation Group on an approximately bimonthly frequency.

Copies of this presentation shall be provided to the Vice President

- Harris Nuclear Project, Plant General

Manager, and others as appropriate.

6.5.4 NUCLEAR ASSESSMENT DEPARTMENT ASSESSMENT PROGRAM 6.5.4.1 Assessments of the following functions/areas will be routinely performed:

'a ~

b.

d.

e.f.

Operations Maintenance Engineering (Design/Modifications/Technical Support)

E&RC (Chemistry/Radiological Controls/Environmental Monitoring)

Fire Protection Nuclear Fuels SHEARON HARRIS - UNIT 1

6-13 Amendment No.

0

~ I

~

4 y

~

~ s,

~

l'

4

" ADMINISTRATIVECONlS 6.5.4 NUCLEAR ASSESSMENT DEPARTMENT ASSESSMENT PROGRAM (Continued)

Assessments of two functions/areas will be performed at the prescribed frequencies:

Emergency Preparedness (PER 10CFR50.54 (t))

Security (PER 10CFR50.54 (p))

6.5.4.2 As part of the overall assessment scheduling activity, the following program elements will be considered and periodically included in the scope of functional assessments.

When several assessments indicate potential problems in a program element, a

special assessment of that element will be performed.

d.

f.

i 0

k.l.

m.

n ~

0.

p q.r.

Control of Heasuring and Test Equipment Control of Purchased Material Equipment and Services Control of Special Processes Corrective Action Document Control Handlinq, Shipping, and Storage Identif>cation and Control of Materials Parts and Components Inspection Inspection,

Test, and Operating Status (Equipment Control)

Instructions, Procedures, and Drawings Nonconforming Materials,

Parts, and Components Organization Outage Management Procurement Document Control Records Test Control Training and gualification The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions.

6.5.4.3 6.5.4.3.1 The NAD Plant Assessment (PA) Section 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 surveillance to verify independently that these activities are performed safely and correctly and that human errors are reduced as much as practical.

The PA Section shall include at least three dedicated, full-time reviewers located on site.

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

Reference:

FSAR Section 17.3.3 6.5. 5 OUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM This section is incorporated into Section 17.3.3.3 of the FSAR.

(PAGE 6-15 DELETED)

(NEXT PAGE IS 6-16)

SHEARON HARRIS - UNIT 1 6-14 Amendment No.

4

, ~ ~. ADMINISTRATIVE CONT S

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 Department and the Vice President

- Harris Nuclear project.

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 Project and the Manager

- Nuclear Assessment Department shall be notified within 24'hours; b.

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; C.

The Safety Limit Violation Report shall be submitted, within 14 days of the violation, to the Commission, the Manager

- Nuclear Assessment Department, and the Vice President

- Harris Nuclear Project; 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.

4 ig

~o

~

, ~.ADMINISTRATIVE CONTR

~S RECORD RETENTION Continued 6.10.3 unit Operat a ~

b.

C.

d.

e.

g.

h.

k.

n.

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

The following records shall be retained for the duration of the ing License:

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 inservice inspections performed pursuant to these Technical Specifications; Records of quality assurance 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 meetings 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 Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later data.

This should include procedures SHEARON HARRIS - UNIT 1

6-25 Amendment No.

nr

,. ~ - ADMINISTRATIVE CONT S

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 performed by the Nuclear Assessment Department.

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 adhered 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.

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 C.

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.

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ML18011A173

Text

Reference:

Reference:

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